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2012 Fermi Power Plant Initial License Examination Proposed Written Exam
	ML12156A295
Person / Time
Site:	Fermi
Issue date:	03/29/2012
From:	Bielby M; Operations Branch III
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ML11354A138	List: ML12156A279; ML12156A286; ML12156A295; ML12156A304; ML12156A313; ML12172A185;
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EXAMINATION 2012 ILO Exam - RO 1 ID: RO1 Points: 1.00 The plant is operating at 100% CTP and at the 100% rod line with APRM/OPRM #2 bypassed. The North RR MG Set speed begins to decrease. The scoop tube is locked per 20.138.03 Uncontrolled Recirc Flow Change. No additional actions have been completed.

The following conditions are observed:

3D107 OPRM INOP is alarming

Total Rated Core flow is 40%

What action is required and the basis for this action? (see attached Power-to-Flow Map)

A. Increase core flow to restore operation outside the "Exit" Region Sufficient margin may not be available for the operator response to suppress potential power oscillations.

B. Insert control rods to restore operation outside the "Exit" Region.

Sufficient margin may not be available for the operator response to suppress potential power oscillations.

C. Trip the North RR MG Set because the change of >10% could cause concerns with MCPR and possible fuel cladding failure due to PCI failure.

D. Place Reactor Mode Switch in SHUTDOWN to terminate the potential for unacceptable power oscillations.

Answer: D Answer Explanation:

With the OPRM inoperable and the reactor operating in the "Scram" region or if the core thermal-hydraulic instability is detected, then unacceptable power oscillations may result. Therefore, the reactor mode switch must be immediately placed in the shutdown position to terminate the potential for unacceptable power oscillations.

ILO EXAM Page: 1 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26758 User-Defined ID: RO1 Cross Reference NEW Number:

Perform immediate actions for Uncontrolled Recirc Topic:

Flow Change Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because you are in the "scram" region for the given conditions. This would be a valid action and basis for in the "exit" region.

B. is incorrect because you are in the "scram" region for the given conditions. This would be a valid action and basis for in the "exit" region.

C. is incorrect because the North RR MG Set speed decreased, not increased. This is a valid action for a

>10% increase.

Reference:

20.138.03 Bases, page 3 Question 1 Table-Item Links Plant Procedures 20.138.03 20.138.03 Bases NUREG 1123 KA Catalog Rev. 2 295001 AK3.04 3.4/3.6 Reactor SCRAM ILO EXAM Page: 2 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Without reference perform AOP immediate actions.

ILO EXAM Page: 3 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 2 ID: R02 Points: 1.00 Following a loss of 120 KV, both EDG 11 and EDG 12 are running and loaded. What is the status of the ESF 130VDC Electrical Distribution System, and what actions, if any, are required to restore?

A. Both DIV 1 and DIV 2 130VDC Chargers continue to supply loads. No operator actions required.

B. DIV 1 130VDC Batteries and DIV 2 130VDC Chargers continue to supply loads. Place tripped Div 1 130VDC Battery Chargers in OFF/RESET, then ON.

C. DIV 1 130VDC Chargers and DIV 2 130VDC Batteries continue to supply loads. Place tripped Div 2 130VDC Battery Chargers in OFF/RESET, then ON.

D. Both DIV 1 and DIV 2 130VDC Batteries continue to supply loads.

Place tripped DIV1 and Div 2 130VDC Battery Chargers in OFF/RESET, then ON.

Answer: B Answer Explanation:

Div 1 130VDC Battery Chargers 2A-1 and 2A1-2 are both powered from MCC 72B-2A and Battery Charger 2A-1 is powered from MCC 72C-3A, which are immediately powered by the EDGs. Upon the initial loss of power the CR1 relay will drop out preventing the automatic restart of the battery charger. Therefore once the EDGs supplies power to the busses, all that is required to restart the battery chargers are to take the CMC to Off/Reset.

ILO EXAM Page: 4 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26719 User-Defined ID: R02 Cross Reference NEW Number:

Status of the ESF 130VDC System on Loss of 120kV Topic:

and actions required to restore Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because DIV 1 chargers lose power, do not auto sequence back on, and must be restored within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C. is incorrect because this would be true for a loss of 345KV.

D. is incorrect because this would be true for a SBO.

Reference:

20.300.120kv, page 25 Question 2 Table-Item Links Plant Procedures 20.300.120kv NUREG 1123 KA Catalog Rev. 2 295003 AA1.04 3.6/3.7 D.C. electrical distribution system Associated objective(s):

Given a copy of the following AOPs: Loss of 345Kv, 120Kv, Offsite Power, and Station Blackout, determine which equipment will be restored and which will remain without power until full system restoration.

ILO EXAM Page: 5 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 3 ID: R03 Points: 1.00 The plant is operating at full power when the following annunciators and indications are received:

9D17, DIV I ESS 130 V BATTERY 2PA TROUBLE

9D21, DIV I EDG SEQUENCER TROUBLE

1D6, DIV I CSS LOGIC POWER FAILURE

1D8, RHR LOGIC A 125 VDC BUS POWER FAILURE

1D62, STM LK DET HPCI LOGIC POWER FAILURE

Div I DC powered valves position indicating lights are OFF.

Breaker position indicating lights for Div I ESF Bus breakers are OFF.

Based on these alarms, select the correct DIAGNOSIS AND EFFECT, if any, on Division I EDGs ability to mitigate a Loss of Offsite Power.

A. ONLY the Division I Batteries have been lost. Division I EDGs will NOT START if Offsite Power is LOST.

B. ONLY the Division I Batteries have been lost. Division I EDGs will AUTO START if Offsite Power is LOST.

C. BOTH Division I Battery Chargers AND BOTH Division I Batteries have been lost. Division I EDGs will NOT START if Offsite Power is LOST.

D. BOTH Division I Battery Chargers AND BOTH Division I Batteries have been lost. Division I EDGs will AUTO START if Offsite Power is LOST.

Answer: C Answer Explanation:

Alarms indicate a complete Loss of DC, BOTH Chargers and BOTH Batteries.

With no Batteries, DC power is not available to support EDGs start functions during a Loss of Offsite Power.

ILO EXAM Page: 6 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26738 User-Defined ID: R03 Cross Reference 202-0701-000-A016-014 Number:

Topic: Status of EDGs on Loss of Offsite Power Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A is plausible; chargers would maintain DC Voltage, preventing these alarms.

B is plausible; chargers would maintain DC Voltage, preventing these alarms. EDGs will NOT start.

D is plausible; EDGs will NOT start.

References:

9D21, page 1; 20.300.260ESF, page 4; ST-OP-315-0064-001, page 17 Question 3 Table-Item Links Plant Procedures 20.300.260VESF 09D21 09D17 NUREG 1123 KA Catalog Rev. 2 295004 AA2.01 3.2/3.6 Cause of partial or complete loss of D.C. power ILO EXAM Page: 7 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Given a copy of the following AOPs: Loss of 345Kv, 120Kv, Offsite Power, and Station Blackout, determine which equipment will be restored and which will remain without power until full system restoration.

ILO EXAM Page: 8 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 4 ID: R04 Points: 1.00 Following a MANUAL Reactor Scram from 50% power, the following conditions are observed in IPCS:

ALL Turbine Control Valves are SHUT.

Generator Megawatts on has just reached ZERO.

The Main Generator Exciter Field Breaker is CLOSED.

BOTH Main Generator output breakers are CLOSED.

Based on these conditions, which one of the following Turbine Generator Trip signals will initiate?

A. Loss of Field B. Reverse Power C. Generator Differential D. Negative Phase Sequence Answer: B Answer Explanation:

With TCVs SHUT, no steam is being supplied to the Turbine Generator. The Generator is still connected to the grid and will begin motoring. Reverse Power will be sensed by this condition and will generate a Turbine Generator Trip when the 67 relay is energized. Breaker position must be looked up in SOER.

ILO EXAM Page: 9 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26740 User-Defined ID: R04 Cross Reference 315-0128-000-A013-001 Number:

Topic: Turbine Generator Trip Signals Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. would be true if the Main Generator Field Breaker OPENED, or excitation was lost.

C. would be true if an electrical fault condition occurred resulting in Differential Current condition.

D. would be true if a phase open occurred in the Generator Stator. Like the Reverse Power trip, the Negative Phase Sequence trip is time dependent, which is a common misconception.

Reference:

20.000.21 Bases, page 5 Question 4 Table-Item Links Plant Procedures 20.000.21 Bases NUREG 1123 KA Catalog Rev. 2 G2.1.19 3.9/3.8 Ability to use plant computer to evaluate system or component status ILO EXAM Page: 10 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Analyze Main Generator and Excitation response using control room indications and annunciators.

ILO EXAM Page: 11 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 5 ID: R05 Points: 1.00 The plant is operating at 15% power during a startup.

ALL Turbine Control Valves OPENED due to an electrical malfunction resulting in a Reactor Scram. No operator actions have been taken.

Which one of the following lists the systems available for Decay Heat Removal IMMEDIATELY after the scram?

A. Safety Relief Valves and Reactor Water Cleanup ONLY.

B. Turbine Bypass Valves, Safety Relief Valves, and Reactor Water Cleanup ONLY.

C. Main Steam Line Drain Valves, Turbine Bypass Valves, and Safety Relief Valves ONLY.

D. Main Steam Line Drain Valves, Turbine Bypass Valves, Safety Relief Valves, and Reactor Water Cleanup.

Answer: A Answer Explanation:

Power at 15% indicates Mode Switch in run. TCVs opening lowers RPV Pressure.

When pressure reaches 756 psig with Mode Switch in run, a GP1 PCIS isolation occurs and a Scram. With MSIVs closed, only SRVs and RWCU are immediately available to remove decay heat.

ILO EXAM Page: 12 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26742 User-Defined ID: R05 Cross Reference 215-0048-000-A018 Number:

Systems available for Decay Heat Removal following Topic:

a scram.

Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because Turbine Bypass Valves are not available.

C. is incorrect because Turbine Bypass Valves and MSL Drains are not available.

D. is incorrect because Turbine Bypass Valves and MSL Drains are not available.

Reference:

20.000.21 Bases, page 2 Question 5 Table-Item Links Plant Procedures 20.000.21 20.000.21 Bases NUREG 1123 KA Catalog Rev. 2 295006 AK1.01 3.7/3.9 Decay heat generation and removal ILO EXAM Page: 13 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Perform proper system operations in accordance with System Operating Procedures (SOP).

ILO EXAM Page: 14 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 6 ID: R06 Points: 1.00 Which one of the following correctly identifies the RCIC controls or indications available at BOTH the Main Control Room AND the Remote Shutdown Panel?

A. RCIC Pump Flow indication.

B. RCIC Pump Discharge Pressure indication.

C. E5150-F010, RCIC Pump CST Suction Isolation Valve, control pushbuttons.

D. RCIC Pump Flow controller with Manual and Automatic Setpoint Adjustments.

Answer: A Answer Explanation:

RCIC Flow Indication exists at both locations.

ILO EXAM Page: 15 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 6 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26744 User-Defined ID: R06 Cross Reference 315-0044-000-A013-001 Number:

Topic: Identify remote controls for the RCIC System.

Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because it exists only in the MCR.

C. is incorrect because it exists only in the MCR.

D. is incorrect because it exists only in the MCR.

Reference:

20.000.19, page 6 Question 6 Table-Item Links Plant Procedures 20.000.19 NUREG 1123 KA Catalog Rev. 2 295016 AK2.01 4.4*/4.5* Remote shutdown panel: Plant-Specific Associated objective(s):

Identify associated remote and local instrumentation, indications, alarms, and controls for the RCIC System.

ILO EXAM Page: 16 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 7 ID: R07 Points: 1.00 The plant is operating at 65% with the following conditions:

North TBCCW pump tripped.

Center TBCCW pump tripped.

Which one of the following would allow the starting of the South TBCCW pump IAW 20.128.01, Loss of TBCCW?

A. TBCCW Heat Exchanger Discharge Temp is 90°F.

B. Head Tank Level is -20 inches indicated.

C. Pump Suction Pressure is 5 psig.

D. Loss of 72N.

Answer: A Answer Explanation:

Temperature is above the entry condition, and allows for a start of the pump.

ILO EXAM Page: 17 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 26746 User-Defined ID: R07 Cross Reference NEW Number:

Topic: Starting requirements for single TBCCW pump.

Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because this is below the trip set point for the pump (-18 inches).

C. is incorrect because this is below the trip set point for the pump (7 psig).

D. is incorrect because this is the power supply for the South Pump.

Reference:

23.128, page 4 Question 7 Table-Item Links Plant Procedures 23.128 NUREG 1123 KA Catalog Rev. 2 295018 AK3.04 3.3/3.3 Starting standby pump Associated objective(s):

Perform proper system operations in accordance with System Operating Procedures (SOP).

ILO EXAM Page: 18 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 8 ID: R08 Points: 1.00 The plant is operating at 100% power with the following Station Air Compressor lineup:

East Station Air Compressor ................. Off

Center Station Air Compressor ..............Running

West Station Air Compressor ............... Auto Following a seismic event, Bus 72A has been de-energized, and both Control Air Compressors auto start. What is the status of the Station Air Compressors?

A. Center Station Air Compressor running, West Station Air Compressor running B. Center Station Air Compressor running, West Station Air Compressor NOT running C. Center Station Air Compressor NOT running, West Station Air Compressor running D. Center Station Air Compressor NOT running, West Station Air Compressor NOT running Answer: B Answer Explanation:

72 A is the power supply to West, with pressure dropping less than 85 psig (indicative of CAC auto start). the West should start, the Center t will remain running.

ILO EXAM Page: 19 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26748 User-Defined ID: R08 Cross Reference NEW Number:

Topic: Status of Station Air Compressors during loss of 72A.

Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because the west cannot start due to loss of power.

C. is incorrect because the center will still have power.

D. is incorrect because the center will still have power.

References:

20.300.72AAttachment 1, page 1; 20.129.01, page 3, 23.129 page 5 Question 8 Table-Item Links Plant Procedures 20.129.01 20.300.72A NUREG 1123 KA Catalog Rev. 2 295019 AA1.03 3/3 Instrument air compressor power supplies Associated objective(s):

Describe general Compressed Air System operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 20 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 9 ID: R09 Points: 1.00 The plant is in HOT SHUTDOWN, with the following conditions:

Reactor Pressure is 25 psig.

RPV Water Level is 250 inches.

RHR Pump B is operating in Shutdown Cooling Mode.

2D26, DIV II RHR SYSTEM LOW FLOW BYPASS INITIATED, alarms due to an electrical fault.

Which one of the following describes the effect on pump flow and continued RHR Loop B Shutdown Cooling operation?

A. DIV 2 RHR pump B Flow will increase; Reactor Water Level will lower until Shutdown Cooling isolates.

B. DIV 2 RHR pump B Flow will remain the same; RHR Loop B will remain operating in Shutdown Cooling with this condition.

C. DIV 2 RHR pump B Flow will decrease; Reactor Water Level will lower until Shutdown Cooling isolates.

D. DIV 2 RHR pump B Flow will increase; RHR Heat Exchanger Bypass Valve has opened; Reactor Coolant System flow will decrease until Shutdown Cooling isolates.

Answer: A Answer Explanation:

The alarm 2D26 indicates the RHR pumps min flow valve has opened resulting in increased pump flow (two paths). The min flow valve will reject Rx water to the Torus causing level to lower until a low Rx water level isolation is reached.

ILO EXAM Page: 21 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26798 User-Defined ID: R09 Cross Reference 315-0041-000-A016-002 Number:

Effect of Min Flow valve open on RHR Shutdown Topic:

Cooling operation Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because the alarm indicates the min flow valve has opened which will affect flow and level.

C. is incorrect because RHR pump flow will increase.

This could be confused with RHR Loop flow which would slightly decrease as a result of the min flow valve opening.

D. is incorrect because it could identify a misconception about the word BYPASS in the alarm title. If the RHR HX were fully BYPASSED, coolant system flow would increase with no isolation.

References:

2D26, page 1; 3D79, page 1 ILO EXAM Page: 22 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 9 Table-Item Links Plant Procedures 03D079 02D026 NUREG 1123 KA Catalog Rev. 2 295021 AA2.02 3.4/3.4 RHR/shutdown cooling system flow Associated objective(s):

Given RHR System performance data, detect abnormalities, and determine possible causes for performance problems.

ILO EXAM Page: 23 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 10 ID: R10 Points: 1.00 An irradiated fuel bundle is being removed from the core. An adjacent bundle has been lifted along with the selected bundle. When noticed, fuel movement is stopped, and the adjacent bundle falls back into the core.

Bubbles come to the pool surface, and the local Continuous Air Monitor (CAM) alarms.

The following indications are observed:

16D1, RB REFUELING AREA FIFTH FLOOR HIGH RADN, alarms.

D21-R600 Radiation Monitoring Recorder, Channel 17 indicates 100 mr/hr.

D21-K717, RB5 Refuel Floor Lo Range ARM Ind trip Unit (Ch. 17), indicates tripped.

No other alarms are received.

What automatic actions, if any, would occur as a result of this event?

A. No automatic actions occur.

B. RBHVAC trips, Div 1 SGTS Auto Starts, CCHVAC aligns in Recirc Mode.

C. RBHVAC trips, both divisions of SGTS Auto Start, CCHVAC aligns in Recirc mode.

D. Group 14-Drywell and Suppression Pool Ventilation System and Group 16-Nitrogen Inerting System isolation.

Answer: A Answer Explanation:

Area radiation monitors provide alarm only. 16D1 requires AOP entry and plant announcement.

ILO EXAM Page: 24 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26799 User-Defined ID: R10 Cross Reference 802-2001-000-0009-003 Number:

Topic: RBHVAC Auto Actions Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 11 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because these actions are associated with Division 1 radiation upscale trips.

C. is incorrect because these actions are associated with Reactor building Vent Exhaust Rad Monitor Upscale Trip or Fuel Pool Vent Exhaust Rad Monitor Upscale Trip.

D. is incorrect because these actions are associated with Reactor building Vent Exhaust Rad Monitor Upscale Trip or Fuel Pool Vent Exhaust Rad Monitor Upscale Trip.

Reference:

20.710.01, page 3 Question 10 Table-Item Links Plant Procedures 16D01 20.710.01 NUREG 1123 KA Catalog Rev. 2 G2.4.45 4.1/4.3 Ability to prioritize and interpret the significance of each annunciator or alarm ILO EXAM Page: 25 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Describe general Reactor Building HVAC System operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 26 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 11 ID: R11 Points: 1.00 The plant is operating at 50% power when a loss of Drywell Cooling occurs. The following sequence is observed:

1205 - 3D81, PRIMARY CONTAINMENT PRESSURE HIGH/LOW alarmed.

- Drywell Pressure indicated 1.50 psig.

1206 - 8D41, DIV I DRYWELL TEMPERATURE HIGH alarmed.

- 17D41, DIV II DRYWELL TEMPERATURE HIGH alarmed.

- Average Drywell Temperature was 142°F.

1300 - Drywell Pressure was lowered by venting, clearing alarm 3D81.

1320 - Drywell Cooling was restored, clearing alarms 8D41 and 17D41.

1340 - The following indications are observed:

- Drywell Pressure is -0.09 (minus 0.09) psig.

- Drywell Temperature is 120°F.

Which one of the following describes the OPERABILITY of the Primary Containment, with respect to Temperature and Pressure, during this evolution?

A. The Primary Containment was maintained OPERABLE throughout this evolution and no actions are required.

B. The Primary Containment was rendered INOPERABLE due to Low Drywell Pressure only, and remains INOPERABLE.

C. The Primary Containment was rendered INOPERABLE due to Low Drywell Pressure and High Average Temperature, and remains INOPERABLE.

D. Primary Containment was rendered INOPERABLE due to High Average Temperature AND High Drywell Pressure, and Required Actions were met within the Completion Time.

Answer: A Answer Explanation:

LCO 3.6.1.4 Low Primary Containment Pressure was NOT exceeded during the evolution (-0.10 psig) and the containment remains OPERABLE.

ILO EXAM Page: 27 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26800 User-Defined ID: R11 Cross Reference 315-0016-000-0013-001 Number:

Topic: Operability of Primary Containment Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 9 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because Drywell Pressure is not below the TS required containment pressure.

C. is incorrect because Drywell Temperature never exceeded the 145°F limit D. is incorrect because Drywell Temperature never exceeded 145°F and Drywell Pressure never exceeded 2.0 psig.

Reference:

Tech Spec 3.6.1.4 Question 11 Table-Item Links NUREG 1123 KA Catalog Rev. 2 295024 EK1.01 4.1/4.2* Drywell integrity: Plant-Specific Technical Specifications 3.6.1.4 Primary Containment Pressure Associated objective(s):

Given plant conditions that constitute non-compliance with any LCO, apply Technical Specifications and Bases to determine the applicable Condition(s),

Required Action(s), and associated Completion Time(s).

ILO EXAM Page: 28 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 12 ID: R12 Points: 1.00 The plant is operating at 90% power. The #1 pressure regulator is in service and you are asked to raise the setpoint 1 PSI. When you take your finger off of the raise button, the button stays depressed and you are unable to release it from this position.

Which of the following describes the response of the plant with NO OPERATOR ACTION?

A. Reactor pressure will lower and the reactor will scram on MSIV closure.

B. Reactor pressure will raise and the reactor will scram on high reactor pressure.

C. The #2 pressure regulator will take over and control reactor pressure approximately 3.5# below the setpoint of the #1 regulator.

D. The #2 pressure regulator will take over and control reactor pressure approximately 3.5# above the setpoint of the #1 regulator.

Answer: B Answer Explanation:

Raising the setpoint of the pressure regulator will result in reactor pressure increasing until the High Reactor Pressure Scram setpoint in reached.

ILO EXAM Page: 29 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26801 User-Defined ID: R12 Cross Reference 315-0145-000-A016-001 Number:

Topic: Pressure Regulator failure - setpoint rising Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 6 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because lowering the pressure regulator setpoint would result in reactor pressure lowering.

C. is incorrect because this is the result of the pressure regulator signal failing low and indicated pressure would be above the setpoint as opposed to below.

D. is incorrect because this is the result of the pressure regulator signal failing low with indicated pressure controlling 3.5 psi higher.

References:

22.000.03, page 15; 20.109.02, page 3 Question 12 Table-Item Links Plant Procedures 20.109.02 22.000.03 NUREG 1123 KA Catalog Rev. 2 295025 EK2.08 3.7/3.7 Reactor/turbine pressure regulating system: Plant-Specific ILO EXAM Page: 30 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Describe general Governor/Pressure Control System operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 31 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 13 ID: R13 Points: 1.00 At 12:00 the plant is operating at 100% power with Torus Water Average Temperature at 78°F when a single SRV opens and all subsequent actions fail to close the SRV. The stuck open SRV is adding 2°F/minute temperature increase into the torus.

(1) What time MUST the Reactor Mode switch be placed in SHUTDOWN and (2) what is the basis for this action?

A. (1) 12:16 (2) The relief valve tailpipes are not designed for continuous blowdown with the reactor at power, and structural damage could result.

B. (1) 12:14 (2) The relief valve tailpipes are not designed for continuous blowdown with the reactor at power, and structural damage could result.

C. (1) 12:16 (2) This ensures the Reactor is shutdown by control rod insertion before the requirement for boron injection is reached.

D. (1) 12:14 (2) This ensures the Reactor is shutdown by control rod insertion before the requirement for boron injection is reached.

Answer: C Answer Explanation:

At 110°F the reactor mode switch is placed in shutdown to prevent exceeding the BIIT.

ILO EXAM Page: 32 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26749 User-Defined ID: R13 Cross Reference NEW Number:

Topic: Perform actions for Torus Temp approaching BIIT.

Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because the relief valves are designed for blowdown at full reactor power.

B. is incorrect because this would correlate to a temperature of 106°F and the valves are designed for full power.

D. is incorrect because this would correlate to a temperature of 106°F.

Reference:

20.000.25, page 2 Question 13 Table-Item Links Plant Procedures 29.100.01 SH 2 20.000.25 NUREG 1123 KA Catalog Rev. 2 295026 EK3.05 3.9/4.1 Reactor SCRAM Associated objective(s):

Perform other EOP / AOP actions as directed.

ILO EXAM Page: 33 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 14 ID: R14 Points: 1.00 The reactor was operating at 100% power when a plant transient occurred. Several minutes later the following conditions are observed:

Drywell pressure is 1.4 psig and slowly rising

Drywell temperature is 155°F and slowly rising

Reactor water level is 28 inches Which actions shall be taken to prevent drywell pressure from exceeding the high drywell scram setpoint?

A. Manually initiate both divisions of EECW.

B. Unisolate EECW to and from the drywell.

C. Manually start all single speed drywell cooling fans.

D. Increase cooling water flow using P42-F400, RBCCW Temp Control Vlv in AUTO, or MANUAL.

Answer: C Answer Explanation:

Rx water level is at the less than level 1 setpoint (32") and results in DW single speed fans tripping. DW fans must be restarted to lower temperature and pressure.

ILO EXAM Page: 34 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 4.00 System ID: 26802 User-Defined ID: R14 Cross Reference 802-3004-000-0007-012 Number:

Topic: Drywell Fan operation in EOPs Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because all single speed fans have tripped and cooling water would have no affect on drywell temperature/pressure without fans.

B. is incorrect because a high drywell signal does not exist and with no fans, cooling water would have no impact.

D. is incorrect because all single speed fans have tripped per level 1 signal.

Reference:

29.ESP.01, page 4 Question 14 Table-Item Links Plant Procedures 17D41 29.ESP.01 NUREG 1123 KA Catalog Rev. 2 295028 EA1.04 3.9/4 Drywell pressure ILO EXAM Page: 35 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Describe general Drywell Cooling System operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 36 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 15 ID: R15 Points: 1.00 The plant is operating at 100% power when a leak develops in the Torus. At 12:00 the initial Torus level as indicated on T50-R804 A(B) Torus Level Recorder reads

-1.5 inches and lowering at -0.5 inches per minute. At time 12:20 which instrument(s) should be monitored for EOP entry on Torus Water Temperature?

A. Average Temperature on T23-R800 Suppression Chamber Bulk Water Temperature on H11P601 OR T47-R803A(B) DW Cooling System Temperature Div I (II) on H11P808(P817).

B. Average Temperature on T23-R800 Suppression Chamber Bulk Water Temperature on H11P601.

C. Points 9 and 10 on T50-R800A(B) PC Air & Water Temperature Div I (II) on H11P601(P602).

D. Points 11 and 12 on T50-R800A(B) PC Air & Water Temperature Div I (II) on H11P601(P602).

Answer: D Answer Explanation:

At -11 inches in the Torus, all 8 of the thermocouples providing input to the T23-R800 recorder are uncovered and will indicate air temperature. Water temperature must be obtained from Drywell and Torus Air and Water Temperature Recorders points 11 and 12.

ILO EXAM Page: 37 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.50 System ID: 26750 User-Defined ID: R15 Cross Reference NEW Number:

Topic: Monitor Torus Water Temperature for EOP entry.

Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because at -11 inches, water temperature must be obtained from Drywell and Torus Air and Water Temperature Recorders points 11 and

12. This is plausible if calculation was inaccurate and level was determined to be >-11 inches.

B. is incorrect because at -11 inches, water temperature must be obtained from Drywell and Torus Air and Water Temperature Recorders. This is plausible if calculation was inaccurate and level was determined to be >-11 inches.

C. is incorrect because points 11 and 12 are the correct points to monitor.

Reference:

29.100.01 SH 6, Caution #6 Question 15 Table-Item Links Plant Procedures 29.100.01 SH 6 NUREG 1123 KA Catalog Rev. 2 295030 EA2.02 3.9/3.9 Suppression pool temperature ILO EXAM Page: 38 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Apply notes and cautions as directed by the EOP / AOP.

ILO EXAM Page: 39 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 16 ID: R16 Points: 1.00 The plant was operating at 100% power when a LOCA occurred. The following plant conditions exist:

RPV pressure ................... 900 psig

RPV level .........................155 inches and lowering

Heater Feed Pumps ........... tripped The STA reports that the leak is 1.0 million lb/hr.

Which systems would provide the MINIMUM flow to maintain RPV water level?

Assume all systems are operating at rated flow. (8.34 lbm/gal)

A. HPCI and RCIC B. Both SBFW pumps C. HPCI and both SBFW pumps D. RCIC, both CRD pumps and both SBFW pumps Answer: D Answer Explanation:

29.ESP.01 Pump Capacities Table lists RCIC flow rate at 600 GPM and CRD at 200 GPM/pump and SBFW at 600 GPM/pump. This would total 2,200 GPM total system flows.

2,200GPM

8.34 lbm/gal

60 mins = 1.1 million lbm/hr.

ILO EXAM Page: 40 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26818 User-Defined ID: R16 Cross Reference 802-3003-000-0111-002 Number:

Topic: Determine Required Flow needed for Leak Size Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this would total 2 8 million lbm/hr.

B. is incorrect because this would total 0 6 million lbm/hr.

C. is incorrect because this would total 3 1 million lbm/hr.

Reference:

29.ESP.01, page 50 Question 16 Table-Item Links Plant Procedures 29.ESP.01 NUREG 1123 KA Catalog Rev. 2 G2.4.6 3.7/4.7 Knowledge of EOP mitigation strategies Associated objective(s):

Apply notes and cautions as directed by the EOP / AOP.

ILO EXAM Page: 41 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 17 ID: R17 Points: 1.00 During an ATWS emergency event, the following conditions exist:

Reactor power .............. above APRM Downscale Setpoint

RPV water level ............ in level band + 50 to + 100 inches

RPV pressure ..................................................... 550 psig

SLC Pumps ..................................................... inoperable

SBFW System .................... being used for boron injection Given the above conditions, identify which of the following the operating crew can use to determine that Hot Shutdown Boron Weight has been injected to the reactor.

A. SLC tank level is <45".

B. IRMs indicate downscale.

C. 1290 lbs of Borax and 1290 lbs of Boric Acid have been added.

D. 3215 lbs of Borax and 3215 lbs of Boric Acid have been added.

Answer: C Answer Explanation:

1290 lbs of Borax and 1290 lbs of Boric Acid are the requirements to achieve the hot shutdown boron weight.

ILO EXAM Page: 42 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 26751 User-Defined ID: R17 Cross Reference 802-3002-000-0008-003 Number:

Topic: Determine Hot Shutdown Boron Weight.

Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because SLC pumps are inoperable. It was once a method of alternate boron injection.

B. is incorrect because IRM indication is not a valid means to determine hot shutdown boron weight.

D. is incorrect because this is the amount used to determine cold shutdown boron weight.

Reference:

29.100.01 SH 1A, Table 15 Question 17 Table-Item Links Plant Procedures 29.100.01 SH lA NUREG 1123 KA Catalog Rev. 2 295037 EK1.03 4.2/4.4* Boron effects on reactor power (SBLC)

Associated objective(s):

Apply notes and cautions as directed by the EOP / AOP.

ILO EXAM Page: 43 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 18 ID: R18 Points: 1.00 Following a Main Steam Line Break from full power, the Offsite Release Rate has been exceeded. 3D45, CONT CENTER MAKEUP AIR RADN MONITOR UPSCALE TRIP alarms.

Div 1 CCHVAC Makeup Air Radiation Monitor, D11-K809 reads 600 cpm.

Div 2 CCHVAC Makeup Air Radiation Monitor, D11-K813 reads 700 cpm.

Which one of the following actions is correct?

A. OPERATE CCHVAC in the Purge Mode to maximize dilution.

B. SHUTDOWN BOTH CCHVAC Emergency Makeup Fans to reduce the main control room pressure.

C. OPERATE CCHVAC in the Recirculation Mode using ONE Emergency Makeup Fan to optimize filtration.

D. OPERATE CCHVAC in the Recirculation Mode using BOTH Emergency Makeup Fans to maximize filtration.

Answer: C Answer Explanation:

High radiation conditions require CCHAVC in RECIRC Mode. Since the emergency fans are sized for 100% capacity, filtration is optimized by operating ONE make up Fan. High radiation conditions require CCHAVC in RECIRC Mode. Since the emergency fans are sized for 100% capacity, filtration is optimized by operating ONE make up Fan.

ILO EXAM Page: 44 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26975 User-Defined ID: R18 Cross Reference 315-0173-000-0005-001 Number:

Topic: CCHVAC Emergency Makeup Fan Num Field 1: LOK H Num Field 2: 10 CFR 44.41 (b) 5 Text Field: 2012 ILO Exam Comments: Plausible Distractors:

A is plausible; would be true for a smoke condition in the control room.

B is plausible; normal CCHVAC intake fans are shutdown to reduce radioactivity intake.

D is incorrect because AOP Bases state that dual fan operation reduces radionuclide residence time in the Charcoal Filter Trains, reducing filtration.

Reference:

20.000.02, page 5 Question 18 Table-Item Links Plant Procedures 20.000.02 03D045 NUREG 1123 KA Catalog Rev. 2 295038 EK2.07 3.5/3.7 Control room ventilation.

ILO EXAM Page: 45 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Describe general Control Center HVAC system operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 46 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 19 ID: R19 Points: 1.00 During 20.000.18, Control of the Plant from the Dedicated Shutdown Panel, SBFW injection to the RPV must take place within of the reactor scram based on A. 10 minutes; the predicted amount of time it will take to uncover the reactor core assuming an isolated reactor with no makeup water.

B. 10 minutes; the predicted amount of time it would take to startup CTG 11-1, align electrical power to SBFW, and align SBFW for injection assuming a loss of 120 kV mat power.

C. 29 minutes; the predicted amount of time it will take to uncover the reactor core assuming an isolated reactor with no makeup water.

D. 29 minutes; the predicted amount of time it would take to startup CTG 11-1, align electrical power to SBFW, and align SBFW for injection assuming a loss of 120 kV mat power.

Answer: C Answer Explanation:

An analysis has been performed assuming an isolated reactor with no makeup water. This analysis predicts that it will take more than 29 minutes before the reactor core is uncovered.

ILO EXAM Page: 47 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 26760 User-Defined ID: R19 Cross Reference 802-2001-000-R006-010 Number:

Explain basis for SBFW injection w/in 29 minutes Topic:

during 20.000.18.

Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because 10 minutes is how long it would take to start a peaker.

B. is incorrect because 10 minutes is how long it would take to start a peaker D. is incorrect because bases is incorrect.

Reference:

20.000.18 Bases, page 3 Question 19 Table-Item Links Plant Procedures 20.000.18 20.000.18 Bases NUREG 1123 KA Catalog Rev. 2 600000 AK3.04 2.8/3.4 Actions contained in the abnormal procedure for plant fire on site Associated objective(s):

Explain bases for notes and cautions.

ILO EXAM Page: 48 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 20 ID: R20 Points: 1.00 During startup, the plant is operating at 27% power. The Systems Operations Center notifies Fermi 2 that there is potential for degraded grid conditions due to erratic reactive loading in Monroe County. The following conditions are observed:

4D132, Generator Frequency High/ Low is alarming.

Currently the frequency is 58 Hz.

Which of the following actions is required?

A. Adjust voltage to raise frequency back to 60 hz in accordance with 4D132.

B. Trip the main turbine and perform actions in accordance 20.109.01.

C. Scram the reactor and perform actions in accordance with 20.000.21.

D. Start CTG 11-1 in accordance with 23.324.

Answer: B Answer Explanation:

With generator frequency less than 58.2% and power less than 30%,

20.300.GRID directs tripping the turbine.

ILO EXAM Page: 49 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26761 User-Defined ID: R20 Cross Reference 202-1103-000-A001-009 Number:

Topic: Actions required for Degraded Grid Conditions Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because frequency is too low, but this is how you would adjust.

C. is incorrect because reactor power is less than 30%.

D. is incorrect because this is not required, but could be used for supplemental power.

Reference:

20.300.GRID, page 7 Question 20 Table-Item Links Plant Procedures 20.300.GRID NUREG 1123 KA Catalog Rev. 2 700000 AA1.02 3.8/3.7 Turbine/generator controls Associated objective(s):

Given a copy of electrical AOPs, analyze and determine which have immediate actions.

ILO EXAM Page: 50 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 21 ID: R21 Points: 1.00 During a Loss of Condenser Vacuum, the following alarm status exists:

4D108, CONDENSER PRESSURE HIGH is alarming.

4D46, MAIN TURBINE TRIPPED is alarming.

3D86, MN STM LINE ISO VALVE CLOSURE CHANNEL TRIP is alarming.

5D46, N/S RFPT EXHAUST PRESSURE TRIP/FAULT is CLEAR.

These alarms are consistent with which one of the following Main Condenser Backpressure values?

A. 2.5 psia B. 5.0 psia C. 7.0 psia D. 12.5 psia Answer: C Answer Explanation:

With pressure greater than 6.85 psia, you will get 4D108, turbine trip, and MSIV closure, but not feed pump trip.

ILO EXAM Page: 51 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 26838 User-Defined ID: R21 Cross Reference 315-0032-000-0001-001 Number:

Topic: Loss of Condenser Vacuum pressure setpoints Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because the turbine has tripped and MSIV closure.

B. is incorrect because MSIV closure.

D. is incorrect because there is no feed pump tripped alarm.

Reference:

20.125.01, page 2 Question 21 Table-Item Links Plant Procedures 20.125.01 NUREG 1123 KA Catalog Rev. 2 295002 AA1.04 3.3/3.4 PCIS/NSSSS Associated objective(s):

List the automatic features of Primary Containment Isolation System operations.

ILO EXAM Page: 52 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 22 ID: R22 Points: 1.00 The plant was operating at full power, when the following occurred:

Both Feedwater Pumps Tripped.

The reactor automatically scrammed.

One Control Rod is at position 48. All other Control Rods are fully inserted.

RCIC is isolated.

HPCI initiation RAISED RPV Water Level from 110 inches. HPCI was manually tripped as RPV Water Level reached 210 inches.

Plant conditions are currently:

Reactor pressure 700 psig, rising at 10 psig per minute.

MSIVs are OPEN.

The operating CRD Pump tripped.

What is the expected RPV Water Level response over the next ten minutes, and what action will be required?

Over the next ten minutes, RPV Water Level will A. RISE due to swell. It is required to allow steam off to lower RPV Water Level BELOW 214 inches.

B. LOWER due to shrink. It is required to use HPCI to maintain RPV Water Level ABOVE 173.4 inches.

C. LOWER due to shrink. It is required to use only RCIC to maintain RPV Water Level ABOVE 0 inches.

D. RISE due to swell. It is required to TERMINATE AND PREVENT Injection Systems to lower RPV Water Level BELOW 114 inches.

Answer: A Answer Explanation:

HPCI injected (100 inches x 200 gal per inch) 20,000 gallons of cold CST water.

As this water is heated, SWELL occurs. It is required to maintain RPV Water level below Level 8 (214 inches). The SRO is required to direct operators to allow steaming to lower RPV Water Level. Shrink cannot occur because heatup and pressurization of saturated system is in progress with NO steam voids. All SRVs and TBVs are shut for the next ten minutes because reactor pressure will be below 800 psig.

ILO EXAM Page: 53 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26839 User-Defined ID: R22 Cross Reference 802-3003-000-0011-003 Number:

Topic: RPV Water Level Response Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 5 Text Field: 2012 ILO Exam Comments: B. is plausible ; identifies misconception about shrink and swell.

C. is plausible; identifies misconception about shrink and swell. 0 inches is the MINIMUM for the ATWS RPV Water Level Control Band. ATWS is plausible because One Control Rod did not fully insert.

D. is plausible, 114 inches is the maximum for the ATWS RPV Water Level Control Band. ATWS is plausible because ONE Control Rod did not fully insert.

Question 22 Table-Item Links Plant Procedures 23.107 NUREG 1123 KA Catalog Rev. 2 295008 AA2.05 2.9/3.1 Swell Associated objective(s):

Monitor critical parameters.

ILO EXAM Page: 54 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 23 ID: R23 Points: 1.00 During a transient, Drywell Pressure is 3.0 psig, Drywell Temperature is 232°F, and all single speed Drywell Coolers are TRIPPED.

Which one of the following responses is correct, and why?

A. Do NOT attempt to restart Drywell Coolers, to prevent piping damage.

B. Restart all available Drywell Coolers, to lower Drywell Temperature and Pressure.

C. Do NOT attempt to restart Drywell Coolers, to prevent cycling the Reactor Building to Torus Vacuum Breakers.

D. Defeat High Drywell Pressure isolation of RBCCW and restart all available Drywell Coolers, to lower Drywell Temperature and Pressure.

Answer: D Answer Explanation:

With Drywell Temperature below 242°F, defeat isolation, restore RBCCW and restart drywell coolers.

ILO EXAM Page: 55 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26840 User-Defined ID: R23 Cross Reference 802-3005-000-0009-012 Number:

Perform actions to lower Drywell Temperature and Topic:

Pressure Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because DW temperature is not above the design limit of 242°F.

B. is incorrect because DW temperature is not above 242°F and flow to and from the drywell coolers has been isolated when DW/P >1.68 psig.

C. is incorrect because spray below the DWSIL curve may cause RB to Torus Vacuum Breakers OPEN.

References:

29.100.01 SH 2, DWT-3; 29.ESP.08, page 3

Question 23 Table-Item Links Plant Procedures 29.ESP.08 29.100.01 SIT 2 NUREG 1123 KA Catalog Rev. 2 295012 AK3.01 3.5/3.6 Increased drywell cooling ILO EXAM Page: 56 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Perform other EOP / AOP actions as directed.

ILO EXAM Page: 57 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 24 ID: R24 Points: 1.00 The plant was operating at 70% rated power when an INCREASE in Main Generator megawatts was observed. The positions of the control rods and recirculation flow rate have not changed.

Which of the following caused the INCREASE in Main Generator megawatts?

A. A Safety Relief Valve has OPENED.

B. A Turbine Bypass Valve has OPENED.

C. #6 Feedwater Heater String Bypass Valve has CLOSED.

D. #6 North Feedwater Heater Extraction Steam Supply Valve has CLOSED.

Answer: D Answer Explanation:

A Feedwater Heater Extraction Steam Supply Valve closing causes increased core inlet subcooling which raises Reactor Power and steam flow to the Main Turbine.

ILO EXAM Page: 58 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 26841 User-Defined ID: R24 Cross Reference 315-0131-000-0005-011(M)

Number:

Topic: Effect of Loss of FW Heating Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because an Open SRV would cause a small increase in reactor power, but a decrease in Main Generator Power.

B. is incorrect because an Open Bypass Valve would cause a small increase in reactor power, but a decrease in Main Generator Power.

C. is incorrect because this is the normal lineup. If it were open it would be true.

Reference:

20.107.02, pages 2 & 7 Question 24 Table-Item Links Plant Procedures 20.107.02 NUREG 1123 KA Catalog Rev. 2 295014 AK2.07 3.9/3.9 Reactor power Associated objective(s):

Discuss the Extraction Steam and Heater Drains System interrelationships with other systems.

ILO EXAM Page: 59 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 25 ID: R25 Points: 1.00 Heavy thunderstorms just caused a load-reject from 100% power. The reactor conditions are:

APRM Power stable at 20%

No indications of control rod position

Recirc pumps tripped

All MSIVs are open

Reactor Level being maintained by feedwater

Reactor Pressure being maintained through Turbine Bypass Valves

Mode switch in SHUTDOWN The CRNSO's FIRST action and the reason for that action should be:

A. Order 29.ESP.11 for MSIVs to prevent possible discharge of radionuclides to the suppression pool.

B. Inhibit ADS to prevent a reactivity addition and possible core damaging power excursion.

C. Bypass and restore drywell pneumatics to maintain the condenser as a heat sink.

D. Terminate and prevent to prevent high core inlet subcooling.

Answer: B Answer Explanation:

FSL-1 DIRECTS Inhibit ADS to prevent a Reactivity Addition and possible core damaging power excursion.

ILO EXAM Page: 60 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.50 System ID: 26842 User-Defined ID: R25 Cross Reference 202-0601-000-0001-035 Number:

Topic: Actions on Load Reject and ATWS Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because it is directed in step FSL-4, which is after inhibiting ADS.

C. is incorrect because it is directed in step FSL-4, which is after inhibiting ADS.

D. is incorrect because it is directed in step FSL-10 or FSL-11, which is after inhibiting ADS.

Reference:

29.100.01 SH 1A, FSL-2 Question 25 Table-Item Links Plant Procedures 29.100.01 SH lA NUREG 1123 KA Catalog Rev. 2 295015 AK1.04 3.8/3.8 Reactor pressure: Plant-Specific Associated objective(s):

Perform other EOP / AOP actions as directed.

ILO EXAM Page: 61 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 26 ID: R26 Points: 1.00 What does 29.ESP.23, Defeat of RBCCW/EECW Cooling Water to Drywell Isolation, inhibit, and when would it be required?

A. Defeats the RBCCW Low Differential Pressure input to EECW/EESW logic It would be directed to be performed for restoration from a loss of offsite and onsite power.

B. Defeats the High Drywell Pressure input to EECW/EESW logic. It would be directed to be performed for restoration from a loss of offsite and onsite power.

C. Defeats the High Drywell Pressure input to EECW/EESW logic. It would be directed to be performed any time there was a leak outside the Drywell.

D. Defeats the RBCCW Low Differential Pressure input to EECW/EESW logic. It would be directed to be performed any time there was a leak outside the Drywell.

Answer: B Answer Explanation:

This procedure provides instructions for defeating the High Drywell Pressure input to EECW/EESW logic to permit restoration of RBCCW/EECW Cooling Water to the Drywell when directed by 20.300.SBO, "Loss of Offsite and Onsite Power (Division 1 only).

ILO EXAM Page: 62 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 26 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 4.00 System ID: 26843 User-Defined ID: R26 Cross Reference NEW Number:

Topic: Restore RBCCW/EECW to Drywell in 20.300.SBO Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because it is not performed when there is a leak outside the Drywell.

C. is incorrect because it does not defeat the RBCCW Low D/P.

D. is incorrect because it does not defeat the RBCCW Low D/P and it is not performed when there is a leak outside the Drywell.

Reference:

29.ESP.23, page 2 Question 26 Table-Item Links Plant Procedures 29.ESP.23 NUREG 1123 KA Catalog Rev. 2 G2.4.34 4.2/4.1 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Associated objective(s):

Describe the three methods of restoring cooling water to the Drywell when Primary Containment pressure is greater than 1.68 psig.

ILO EXAM Page: 63 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 27 ID: R27 Points: 1.00 The plant is operating at 97% power when the plant experiences a seismic event. The following alarms are received:

6D69, SEISMIC SYSTEM EVENT/TROUBLE

2D78, REAC BLDG FLR/EQUIP DRN SUMPS LVL HI-HI/LO-LO

7D10, ELECTRIC FIRE PUMP AUTO START

7D6, DIESEL FIRE PUMP AUTO START G1101-D073, RB NW Equip Drn Sump Level is verified at 47 inches and rising with both sump pumps running. No additional alarms are received. 29.100.01 Sheet 5, Sec Cont/Rad Release has been entered. What action is required?

A. Isolate the leak in Fire Protection System.

B. Place Mode Switch in Shutdown.

C. Assemble the Fire Brigade.

D. Perform GOP shutdown.

Answer: A Answer Explanation:

Indications are given that a leak is coming from the fire protection system.

29.ESP.01 lists the FP system as a possible source for leakage into this sump.

29.100.01 Sheet 5 directs you to isolate systems leaking into secondary containment.

ILO EXAM Page: 64 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 27 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26858 User-Defined ID: R27 Cross Reference NEW Number:

Topic: Actions for Flooding from Fire Proterction System Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because sump level has not exceeded the max safe, and is not a primary system (FP).

C. is incorrect because auto starts of both fire pumps is not positive indication of a fire..

D. is incorrect because sump level has not exceeded the max safe.

References:

29.ESP.01, page 21; 29.100.01 SH 5, SC-2 Question 27 Table-Item Links Plant Procedures 29.100.01 SH 5 29.ESP.01 NUREG 1123 KA Catalog Rev. 2 295036 EA1.02 3.5/3.6 Affected systems so as to isolate damaged portions ILO EXAM Page: 65 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Perform other EOP / AOP actions as directed.

ILO EXAM Page: 66 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 28 ID: R28 Points: 1.00 Choose the statement that describes how water hammer in RHR is minimized or prevented.

A. The RHR suction and discharge piping is maintained full of water by Keep Fill supplied from the Demin System.

B. The RHR discharge piping is maintained full of water by Keep Fill supplied from the Demin System.

C. The RHR discharge piping is maintained full of water by Keep Fill supplied from the Condensate Storage and Transfer System.

D. The RHR suction and discharge piping is maintained full of water by Keep Fill from the Condensate Storage and Transfer System.

Answer: C Answer Explanation:

Justification RHR discharge piping is supplied by CSTS, suction is supplied from torus via gravity.

ILO EXAM Page: 67 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 28 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26898 User-Defined ID: R28 Cross Reference 202-0601-000-0001-035 Number:

Topic: RHR Keep Fill Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because it is not supplied from Demin system B. is incorrect because it is not supplied from the Demin system.

D. is incorrect because the suction is supplied from the Torus.

Reference:

23.205, page 15 Question 28 Table-Item Links Plant Procedures 23.205 NUREG 1123 KA Catalog Rev. 2 203000 K1.04 3.3/3.4 Keep fill system Associated objective(s):

Discuss the RHR System interrelationships with other systems.

ILO EXAM Page: 68 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 29 ID: R29 Points: 1.00 (1) What conditions are the operating crew allowed to close E1100-F060B, Division 2 LPCI Manual Isolation Valve, and (2) what is the reason for this precaution?

A. (1) Modes 3, 4, or 5.

(2) A valve stem failure could result in an unisolatable leak.

B. (1) Modes 3, 4, or 5.

(2) The operators may not be able to reopen the valve due to high dp.

C. (1) RPV depressurized or SM approval.

(2) The operators may not be able to reopen the valve due to high dp.

D. (1) RPV depressurized or SM approval.

(2) A valve stem failure could result in an unisolatable leak.

Answer: D Answer Explanation:

Justification per 23.205 precaution 3.1.8. Unless authorized by the SM, E1100-F060B, Div 2 LPCI Manual Iso Vlv, shall not be closed with RPV pressurized.

The valve stem could fail and cause an unisolatable leak.

ILO EXAM Page: 69 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 29 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26899 User-Defined ID: R29 Cross Reference 202-0501-000-A005-006(M)

Number:

Topic: 3.1.8Precaution of F060 Operation Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because you must have SM approval or be depressuized.

B. is incorrect because you must have SM approval or be depressuized and reason is not correct.

C. is incorrect because the reason not high dp.

Reference:

23.205, precaution 3.1.8 Question 29 Table-Item Links Plant Procedures 23.205 NUREG 1123 KA Catalog Rev. 2 203000 A2.03 3.2/3.3 Valve closures Associated objective(s):

State major precautions and limitations, and major safety considerations for the RHR System, and describe their bases.

ILO EXAM Page: 70 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 30 ID: R30 Points: 1.00 Which one of the following components would be affected by a loss of power from the 2PB bus?

A. E1150-F017B LPCI Loop B Outboard Isolation Valve B. E1150-F015B LPCI Loop B Inboard Isolation Valve C. E1150-F008 Shutdown Cooling Outboard Isolation Valve D. E1150-F009 Shutdown Cooling Inboard Isolation Valve Answer: C Answer Explanation:

Justification it is the only valve given which receives power from 2PB.(2PB1 Pos 5A)

ILO EXAM Page: 71 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 30 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 26900 User-Defined ID: R30 Cross Reference 315-0141-000-A014-003 Number:

Topic: Loss of 2PB Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because it gets power from 72CF.

B. is incorrect because it gets power from 72CF.

D. is incorrect because it gets power from 72C.

Reference:

20.300.260ESF Enclosure B, page 1 Question 30 Table-Item Links Plant Procedures 23.205 20.300.260VESF NUREG 1123 KA Catalog Rev. 2 205000 K2.02 2.5*/2.7* Motor operated valves Associated objective(s):

Describe the normal and alternate power supplies to RHR System components.

ILO EXAM Page: 72 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 31 ID: R31 Points: 1.00 The plant is operating at 94% power during surveillance 24.202.01 HPCI Pump and Valve Operability. After the HPCI turbine comes up to speed, E4150-F012, Pump Min Flow Iso Valve, fails in the open position. Assuming no operator action, explain the effect this will have on Torus water level?

A. Torus water level will rise until suction source switches from Torus to CST.

B. Torus water level will rise until suction source switches from CST to Torus.

C. Torus water level will lower until suction source switches from CST to Torus.

D. Torus water level will lower until suction source switches from Torus to CST.

Answer: B Answer Explanation:

Because the E4150-F012, Pump MM Flow Iso Valve goes back to the Torus, the flowpath would be from the CST to Torus. Level would increase in the Torus until +3 inches, then suction source auto swaps from CST to Torus.

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EXAMINATION 2012 ILO Exam - RO Question 31 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 3.00 System ID: 26901 User-Defined ID: R31 Cross Reference NEW Number:

Topic: Min flow valve failure affect on torus level Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because Level would increase in the Torus until +3 inches, then suction source auto swaps from CST to Torus.

C. is incorrect because Level would increase in the Torus.

D. is incorrect because Level would increase in the Torus.

Reference:

23.202, page 7 Question 31 Table-Item Links Plant Procedures 23.202 NUREG 1123 KA Catalog Rev. 2 206000 K3.03 3.4*/3.5* Suppression pool level control: BWR-2,3,4 Associated objective(s):

Given various system operating parameters, relate system/equipment operation to fundamental concepts to determine proper operation/response as described in the BWR Fundamentals Catalog.

ILO EXAM Page: 74 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 32 ID: R32 Points: 1.00 The plant was operating at 95% power when a LOCA occurred in the drywell. The following plant conditions exist:

Drywell Pressure ................. 2.4 psig

Reactor Pressure .................. 500 psig and lowering What is the status of Div 1 CS Pumps Minimum Flow Bypass Valve, E2150-F031A, and what condition would allow it to reposition?

A. E2150-F031A would be CLOSED. It would open when E2150-F005A, CSS Loop A Inboard Isolation Valve is throttled shut.

B. E2150-F031A would be CLOSED. It would open if A or C Core Spray Pump is secured.

C. E2150-F031A would be OPEN. It would close when E2150-F005A, CSS Loop A Inboard Isolation Valve is opened.

D. E2150-F031A would be OPEN. It would close when Reactor Pressure drops below 245 psig.

Answer: D Answer Explanation:

With a high Drywell Pressure, CS Pumps will start and not inject. The MM Flow Valves will be open unitl flow exceeds 775 gpm. CS aligns for injection at 461 psig, with shutoff head at 285 psig.

ILO EXAM Page: 75 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 32 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 26902 User-Defined ID: R32 Cross Reference NEW Number:

Topic: CS Min flow valve operation Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect for the given conditions, flow would not exceed 775 gpm, the min flow valve would be shut.

B. is incorrect for the given conditions, flow would not exceed 775 gpm, the min flow valve would be shut.

C. is incorrect because FOO5A, CSS Loop A Inboard Isolation Valve opens at 461 psig. The pumps will still be at shutoff head.

Reference:

29.ESP.01, page 50 Question 32 Table-Item Links Plant Procedures 23.203 29.ESP.01 NUREG 1123 KA Catalog Rev. 2 209001 K4.05 2.6/2.6 Pump minimum flow ILO EXAM Page: 76 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Given various system operating parameters, relate system/equipment operation to fundamental concepts to determine proper operation/response as described in the BWR Fundamentals Catalog.

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EXAMINATION 2012 ILO Exam - RO 33 ID: R33 Points: 1.00 Per LCO 3.1.7 Standby Liquid Control Systems, two SLC Subsystems shall be operable in Modes 1 and 2. Why does this LCO not apply in other modes?

A. In Modes 3, 4, and 5, Shutdown cooling will dilute the born concentration.

B. In Modes 3, 4, and 5, all rods are inserted and criticality cannot be achieved.

C. In Mode 4 and 5, temperature is less than 200°F. SLC is ineffective at temperature below 200°F.

D. In Mode 5, only one rod can be withdrawn at a time in a cell containing fuel assemblies. Demonstration of adequate SDM ensures the reactor will not become critical.

Answer: D Answer Explanation:

SLC is not required in Modes 3 and 4 because with the mode switch in SHUTDOWN, no rods can be withdrawn. In mode 5, after verifying the reactor will remain shutdown with the highest rod worth rod fully withdrawn(SDM), one rod may be withdrawn and the reactor will not be critical.(TS B 3.1.7 APPLICABILITY).

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EXAMINATION 2012 ILO Exam - RO Question 33 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 4.00 System ID: 26918 User-Defined ID: R33 Cross Reference NEW Number:

Topic: TS SLC Operabilty Requirements Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect it is the wrong bases. SDC would dilute the SLC boron being injected.

C. is incorrect because temperature may affect the effectiveness, but is still the wrong bases.

B. is incorrect because you can withdraw rods in mode

5. This is the correct bases for modes 3 and 4.

Reference:

Tech Spec 3.1.7 Question 33 Table-Item Links NUREG 1123 KA Catalog Rev. 2 211000 K5.03 3.2/3.5 Shutdown margin Technical Specifications 3.1.7 Standby Liquid Control (SLC) System Associated objective(s):

Describe the Standby Liquid Control System technical specification limiting con-ditions for operation, their bases, the associated surveillance requirement(s), and their relationship to operability.

ILO EXAM Page: 79 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 34 ID: R34 Points: 1.00 An operator standing by a Hydraulic Control Unit (HCU) bank hears a click of multiple solenoid valves changing position, and no sound of air discharging. This is followed by an announcement from the Control Room of the receipt of a 1/2 scram.

Which ONE of the following is the initiating event which leads to this condition?

A. A 1/2 scram of RPS Channel A.

B. A 1/2 scram of RPS Channel B.

C. A 1/2 scram caused one half of the Back-Up Scram Valves to energize.

D. A 1/2 scram caused one half of the Back-Up Scram Valves to de-energize.

Answer: A Answer Explanation:

Justification because when RPS A cause a half scram, solenoids will reposition, no air would vent.

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EXAMINATION 2012 ILO Exam - RO Question 34 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26919 User-Defined ID: R34 Cross Reference 213-0202-000-0001 Number:

Topic: Solenoids reposition during half scram Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect for if RPS B initiated the half scam, air would be vented.

C/D. is incorrect because backup scam valves energize when full scram signal is present.

Reference:

M-5703-1 Question 34 Table-Item Links Plant Drawings M-5703-1 NUREG 1123 KA Catalog Rev. 2 212000 K1.06 3.5/3.6 Control rod drive hydraulic system Associated objective(s):

Given various system operating parameters, relate system/ equipment operation to fundamental concepts to determine proper operation/response as described in the BWR Fundamentals Catalog.

ILO EXAM Page: 81 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 35 ID: R35 Points: 1.00 Which one of the following provides power for the Intermediate Range Channel B instrument drawer?

A. 120/208 VAC Cabinet 72E-2B-1 B. 120 VAC UPS Distribution Cabinet B C. 48/24 VDC DC Distribution Cabinet 2IA1-3 D. 48/24 VDC DC Distribution Cabinet 21131-3 Answer: D Answer Explanation:

Justification because 48/24 VDC Distribution provides power for the IRM Channel B instrument Drawer.

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EXAMINATION 2012 ILO Exam - RO Question 35 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26920 User-Defined ID: R35 Cross Reference 202-0211-000-A003 Number:

Topic: IRM power supplies Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect it is the power supply for IRM B Detector Drive Power.

B. is incorrect it is the power supply for IRM Chart Recorder.

C. is incorrect it is the power supply for IRM Channels A, C, E, and G instrument drawers.

Reference:

20.300.24/48DC Enclosure B Question 35 Table-Item Links Plant Procedures 23.603 20.300.24/48VDC NUREG 1123 KA Catalog Rev. 2 215003 K2.01 2.5*/2.7 IRM channels/detectors Associated objective(s):

Describe the normal and alternate power supplies to Intermediate Range Monitoring System components.

ILO EXAM Page: 83 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 36 ID: R36 Points: 1.00 An upscale failure on SRM(s) (1) will be the MINIMUM required to cause a reactor scram with the shorting links (2) .

A. (1) A ONLY (2) removed B. (1) A AND B (2) removed C. (1) A ONLY (2) installed D. (1) A AND B (2) installed Answer: A Answer Explanation:

Justification this is the minimum to cause a scram. Only one upscale with shorting links removed will cause a scram.

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EXAMINATION 2012 ILO Exam - RO Question 36 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26921 User-Defined ID: R36 Cross Reference 315-0122-000-B007-003 Number:

Topic: Upscale trip causing scram Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect it will cause a scam, but is not the minimum C. is incorrect it will not generate a scram.

D. is incorrect it not cause a scam, but is a common misconception.

Reference:

3D55 Question 36 Table-Item Links Plant Procedures 03D055 NUREG 1123 KA Catalog Rev. 2 215004 K3.01 3.4/3.4 RPS Associated objective(s):

Discuss failure modes of Source Range Monitoring System controls and vital instruments, including design features that could result in erroneous operation or indication.

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EXAMINATION 2012 ILO Exam - RO 37 ID: R37 Points: 1.00 The reactor is operating with BOTH recirculation loops in operation, conditions are as follows:

APRM Flux is 40%.

APRM Recirc Flow is 53%

Total Core Flow is 55 Mlbm/hr, equally divided between both loops.

Which one of the following is the LOWEST APRM power which will produce a Simulated Thermal Power Trip?

A. 87%

B. 90%

C. 95%

D. 114%

Answer: C Answer Explanation:

The APRM Simulated Thermal Power Upscale Trip setpoin is 0.63(W) +61.4%,

with W=45, the trip setpoint is 94.79%. The lowest listed power which exceeds this is 95%.

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EXAMINATION 2012 ILO Exam - RO Question 37 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26922 User-Defined ID: R37 Cross Reference 315-0124-000-A017-006(M)

Number:

Topic: STP 2 loop trip Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this would be true if you used W=40.

B. is incorrect because this would be true if you used W=45.

D. is incorrect because this the High Clamp Value for the APRM STP Trip Setpoint.

Reference:

3D101 Question 37 Table-Item Links Plant Procedures 03D101 NUREG 1123 KA Catalog Rev. 2 215005 K4.07 3.7/3.7 Flow biased trip setpoints Associated objective(s):

Describe general Power Range Neutron Monitoring System operation, including component operating sequence, normal operating parameters, and expected system response.

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EXAMINATION 2012 ILO Exam - RO 38 ID: R38 Points: 1.00 While the RCIC System is operating, the following system conditions exist:

Lube oil temperature ....................................... 150°F

Lube oil pressure .............................................11 psig

E51-F044 (Governor Valve) ............................ cycling

E51-F040 (Turbine Exhaust Check Valve) ........ hammering open and closed Given the above RCIC Systems conditions, identify which of the following is likely causing these problems.

A. High system flow.

B. Lube oil high temperature.

C. Turbine speed below 2100 rpm.

D. The fluid being pumped by the RCIC Pump is too hot.

Answer: C Answer Explanation:

Justification P&L 3.5 states RPM under 2100 causes control valve instability along with water hammer. Both indications are given in the stem.

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EXAMINATION 2012 ILO Exam - RO Question 38 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26938 User-Defined ID: R38 Cross Reference 315-0143-000-0107-001 Number:

Topic: RCIC flow precaution Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect the check valve would not be hammering.

B. is incorrect lube oil temperature rising is a result not cause.

C. is incorrect CST does not get that hot.

Reference:

23.206 P&L 3.5 Question 38 Table-Item Links Plant Procedures 23.206 NUREG 1123 KA Catalog Rev. 2 217000 K5.02 3.1/3.1 Flow indication Associated objective(s):

State major precautions and limitations, and major safety considerations for the RCIC System, and describe their bases.

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EXAMINATION 2012 ILO Exam - RO 39 ID: R39 Points: 1.00 RCIC system has started automatically on Level 2 due to a loss of Feedwater.

Which of the following accurately describes what is sensed by the E51-R613, RCIC Pump Flow Indicator?

A. Flow through the minimum flow bypass valve (E5150-F019).

B. Total system flow from all RCIC Pump flowpaths.

C. RPV injection flow through RCIC Pump Discharge Inboard Isolation Valve (E5150-F013).

D. RCIC Pump test line flow back to the CST through the test line isolation valve (E5150-F022).

Answer: C Answer Explanation:

Justification this flow detector only senses what is going in to the reactor.

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EXAMINATION 2012 ILO Exam - RO Question 39 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26939 User-Defined ID: R39 Cross Reference 315-0143-000-0002-004 Number:

Topic: Flow sensed by the flow indicator Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect it does not sense this flow.

B. is incorrect it does not sense min flow bypass or test.

D. is incorrect it does not sense this flow.

Reference:

M-5709-1 Question 39 Table-Item Links Plant Drawings M-5709-1 RCIC System FOS NUREG 1123 KA Catalog Rev. 2 217000 A4.08 3.7/3.6 System flow Associated objective(s):

Given various system operating parameters, relate system/equipment operation to fundamental concepts to determine proper operation/response as described in the BWR Fundamentals Catalog.

ILO EXAM Page: 91 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 40 ID: R40 Points: 1.00 The plant was operating at 100% power when a loss of feedwater occurred and the following conditions exist:

RPV pressure ............................... 875 psig

HPCI system ............................. inoperable

RCIC system ............................. inoperable

MSIVs ............................ cannot be opened Given the above parameters, the operating crew should inhibit the ADS System under which of the following conditions:

A. 184 rods indicate full in.

B. RPV Level at 31 inches.

C. Only one RHR pump is running.

D. Drywell pressure is less than 1.68 psig indicating there is no leak into the Drywell.

Answer: B Answer Explanation:

Justification 29.100.01 Sheetl Directs this if level is less than 32 inches or ADS timer starts its countdown.

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EXAMINATION 2012 ILO Exam - RO Question 40 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26940 User-Defined ID: R40 Cross Reference 315-0143-000-002-004(M)

Number:

Topic: When to inhibit ADS Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this is not an ATWS.

C. is incorrect this is a condition for ADS to actuate, not a reason for inhibiting D. is incorrect it is not a reason for inhibiting.

Reference:

29.100.01 SH 1, L-5 Question 40 Table-Item Links Plant Procedures 29.100.01 SH 1 NUREG 1123 KA Catalog Rev. 2 218000 K4.01 3.7/3.9 Prevent inadvertent initiatior of ADS logic Associated objective(s):

Given a set of plant conditions/actions taken and a current copy of 29.100.01 Sh 1 through 6, determine which step(s) is (are) to be directed by the CRS.

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EXAMINATION 2012 ILO Exam - RO 41 ID: R41 Points: 1.00 A failure of B21-N681A and B21-N681B resulted in numerous isolations and actuations including Division 1 Group 18 Primary Containment Pneumatic Supply System.

How does a Group 18 Primary Containment Pneumatic Supply System Isolation affect ADS valve actuation?

A. ADS SRVs can only be operated after Drywell Pneumatics have been bypassed and restored.

B. ADS SRVs can only be operated after Emergency Nitrogen bottle supplies are hooked up.

C. ADS SRVs can only be operated at least 5 times.

D. ADS SRVs cannot be operated.

Answer: C Answer Explanation:

Group 18 Isolation limits each ADS valve to at least 5 cycles based on the Accumulator capacity.

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EXAMINATION 2012 ILO Exam - RO Question 41 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 2.00 System ID: 26941 User-Defined ID: R41 Cross Reference NEW Number:

Topic: G18 isolation effect on ADS Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect this is a way to restore, but not the only way.

B. is incorrect this is a way to restore, but not the only way.

D. is incorrect each ADS valve is available for 5 cycles based on the Accumulator capacity.

Reference:

ST-OP-315-0042, page 12 Question 41 Table-Item Links Plant Procedures 23.201 NUREG 1123 KA Catalog Rev. 2 218000 K6.07 3.4/3.5 Primary containment instrumentation Associated objective(s):

Discuss the ADS interrelationships with other systems.

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EXAMINATION 2012 ILO Exam - RO 42 ID: R42 Points: 1.00 While operating at 100% power, the B21-N686A, Main Steam Line A High Flow Detection Pressure Differential Trip Unit Div 1 fails UPSCALE.

Which of the following describes the expected response, if any, of the MSIVs?

A. NO MSIVs will close.

B. ALL MSIVs will close.

C. Only MS Line A Inboard MSIV will close.

D. Only MS Line A Inboard AND Outboard MSIVs will close.

Answer: A Answer Explanation:

Justification each MSL has 4 Trip Units and only one upscale will not cause any MSIV to close.

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EXAMINATION 2012 ILO Exam - RO Question 42 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26942 User-Defined ID: R42 Cross Reference 315-0148-000-0004-022 Number:

Topic: MSL flow detector failed upscale Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect no division 2 upscale.

C. is incorrect only one upscale will not cause any MSIV to close.

D. is incorrect only one upscale will not cause any MSIV to close.

Reference:

23.601, page 14 Question 42 Table-Item Links Plant Procedures 23.601 NUREG 1123 KA Catalog Rev. 2 223002 A1.02 3.7/3.7 Valve closures Associated objective(s):

Describe how the Nuclear Boiler system provides redundancy.

ILO EXAM Page: 97 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 43 ID: R43 Points: 1.00 While operating at 100% power, the following alarm is received:

1D61 SRV OPEN The P603 Operator reports power, pressure, and level are stable. NO Red OPEN lights are on. A report from the relay room is SRV A Tailpipe temperature is 222°F and slowly rising.

What is the cause of the alarm, and what actions are recommended?

A. SRV A is open. Push open button for SRV A, and the close button.

B. SRV A is open. Pull fuses for SRV A to ensure it does not reopen.

C. SRV A is leaking by. Push open button for SRV A, and the close button.

D. SRV A is leaking by. Reactor shutdown, and pressure must be lowered to reset.

Answer: D Answer Explanation:

Based on power, pressure, level report, the SRV did not open. 1D61 actuates on temperature or pressure in the tailpipe. Per 1D61, if the SRV is leaking, General Electric recommends lowering pressure below 200 psig to reset the valve (TMPE-96-0065).

ILO EXAM Page: 98 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 43 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 4.00 System ID: 26971 User-Defined ID: R43 Cross Reference NEW Number:

Topic: Leaky SRV Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect indications given do not support SRVA opened, but these are the correct IAs if it did.

B. is incorrect indications given do not support SRVA opened, but these are the correct Supplemental actions if the SRV will not go shut.

C. is incorrect because these are the IAs for OPEN SRV.

Reference:

1D61 Question 43 Table-Item Links Plant Procedures 23.201 01D61 NUREG 1123 KA Catalog Rev. 2 239002 A2.02 3.1/3.2 Leaky SRV Associated objective(s):

Identify alarm response procedures associated with the Nuclear Boiler system.

ILO EXAM Page: 99 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 44 ID: R44 Points: 1.00 The plant is operating at 100% power with the Feedwater Control System (FWCS) in 3 element control.

Which ONE of the following describes the response of the FWCS to a feed line rupture estimated at 5000 gpm in the A feedwater line?

FWCS will....

A. shift to single element control and raise the speed of both Reactor Feed Pump Turbines.

B. stay in three element control and raise the speed of both Reactor Feed Pump Turbines.

C. shift to single element control and raise the speed of the A Reactor Feed Pump Turbine only.

D. stay in three element control and raise the speed of the A Reactor Feed Pump Turbine only.

Answer: A Answer Explanation:

Justification due to the leak and divergence between A and B feed water detectors, the FWCS will shift to single element. Due to the reduction in total feed flow, level will decrease, and both feed pumps will speed up to increase level.

ILO EXAM Page: 100 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 44 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26972 User-Defined ID: R44 Cross Reference 315-0146-000-A015-004 Number:

Topic: Forced single element Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because FWCS will not stay in three element.

C. is incorrect because FWCS will speed up both feed pumps.

D. is incorrect because FWCS will not stay in three element.

Reference:

ST-OP-315-0046, page 17 Question 44 Table-Item Links Plant Procedures 23.107 NUREG 1123 KA Catalog Rev. 2 259002 A3.04 3.2/3.2 Changes in reactor feedwater flow Associated objective(s):

Discuss potential modes of Feedwater Control System component failures and any industry operating experience related to the failure.

ILO EXAM Page: 101 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 45 ID: R45 Points: 1.00 Which of the following symptoms would be indicative of a high temperature (>255°F) in the SGTS Charcoal Adsorber?

A. Increasing Iodine effluents.

B. Decreasing Iodine effluents.

C. Increasing SGTS flow.

D. Decreasing SGTS flow.

Answer: A Answer Explanation:

Justification as temperatures increase above 255°F, the increased molecular motion makes adsorption more difficult, and iodine which has collected on the carbon surfaces may be driven off.

ILO EXAM Page: 102 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 45 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26973 User-Defined ID: R45 Cross Reference 315-0120-000-0008-004 Number:

Topic: Purpose fans come on at 255°F Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because it would cause the opposite.

C. is incorrect because it would not affect flow.

D. is incorrect because it would not affect flow.

Reference:

ST-OP-315-0020, page 12 Question 45 Table-Item Links Plant Procedures 23.404 NUREG 1123 KA Catalog Rev. 2 261000 K4.02 2.6/2.8 Charcoal bed decay heat removal Associated objective(s):

Discuss the function and purpose of Standby Gas Treatment System components, including their importance to nuclear safety.

ILO EXAM Page: 103 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 46 ID: R46 Points: 1.00 Following a transient, plant conditions are as follows:

Drywell Pressure is 2.25 psig.

8D46 DIV I REACTOR BLDG PRESSURE HIGH / LOW is alarming.

17D46 DIV II REACTOR BLDG PRESSURE HIGH / LOW is alarming.

Reactor Building Pressure is 0 inches water column.

Which one of the following has occurred?

A. Reactor Building HVAC Exhaust Fans are running.

B. Both Trains of Standby Gas Treatment are running.

C. Both Trains of Standby Gas Treatment have failed to start.

D. All Reactor Building HVAC Isolation Dampers have failed to isolate.

Answer: C Answer Explanation:

With a high drywell, both SGTS trains should start and RBHVAC should trip.

The indication of 0 inches of Reactor pressure is a result of RBHAVC tripping(pressure increase) and standby gas not starting(pressure would <-.5 inches).

ILO EXAM Page: 104 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 46 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 26944 User-Defined ID: R46 Cross Reference 315-0120-000-A020-001(M)

Number:

Topic: Indications of RB pressure with SGTS running Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because even with RBHVAC in service, pressure would be negative.

B. is incorrect because pressure would be negative.

D. is incorrect because would have no impact with no ventilation fans running.

Reference:

8D46 Question 46 Table-Item Links Plant Procedures 08D46 NUREG 1123 KA Catalog Rev. 2 261000 A4.03 .3/3 Fan Associated objective(s):

Describe general Standby Gas Treatment System operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 105 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 47 ID: R47 Points: 1.00 Following a Loss of Coolant Accident with an electrical plant malfunction, plant conditions are as follows:

RPV Water Level is 35 inches, LOWERING.

Reactor Pressure is 250 psig, LOWERING.

345 kV Mat Power Indicating Lights are OFF.

EDG 13 is LOADED carrying Bus 65E.

Bus 65F and Bus 14ED Power Indicating Lights are OFF.

Bus 72F and Bus 72ED Power Indicating Lights are OFF.

65F-F6 Breaker is TRIPPED.

65F-F8 Breaker is CLOSED.

Which one of the following lists the electrical procedure which should be executed to provide MAXIMUM Low Pressure ECCS Injection to support 29.100.01, Sheet 1, RPV Control actions?

A. 20.300.65F, Loss of Bus 65F, due to Bus 65F being LOCKED OUT.

B. 20.300.72F, Loss of Bus 72F, due to Bus 72F being LOCKED OUT.

C. 20.307.01, Emergency Diesel Generator Failure, due to EDG 14 failing to start.

D. 20.300.SBO, Loss of Offsite and Onsite Power, due to a combination of electrical malfunctions.

Answer: C Answer Explanation:

A loss of 345kv power indicated in loss of ESF Div 2 AC Power. An EDG 14 START FAILURE has resulted in BUS 65F being de-energized ILO EXAM Page: 106 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 47 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26974 User-Defined ID: R47 Cross Reference 802-2001-000-A000-001 Number:

Topic: Loss of 345 kv effect on ECCS Systems Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because a 65F LOCKOUT condition is excluded by 65F-F8 breaker being CLOSED.

B. is incorrect because a 72F LOCKOUT condition is excluded by 65F-F6 breaker being tripped.

D. is incorrect because a Station Blackout is excluded by DIV 1 ESF Buses energized and EDG 13 LOADED.

Reference:

20.307.01, step H1 Question 47 Table-Item Links Plant Procedures 20.307.01 - EDG Failure NUREG 1123 KA Catalog Rev. 2 G2.4.8 3.8/4.5 Knowledge of how abnormal operating procedures are used with EOPs 262001 K1.01 3.8/4.3* Emergency generators (diesel/jet)

ILO EXAM Page: 107 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Describe how the 120/345KV Switchyards assists in maintaining the critical safety functions.

ILO EXAM Page: 108 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 48 ID: R48 Points: 1.00 A Loss of offsite power has occurred and the following conditions exist:

The reactor has scrammed.

Only EDG 14 has started and has energized its respective ESF bus.

EDGs 11, 12 and 13 have failed to start.

Offsite power has been restored to the 345 kV Matt.

Bus 72R has been energized.

How will the UPS system respond?

A. Loads on Unit A are supplied from the Unit B Rectifier through the Unit A Inverter.

B. Loads on Unit A are supplied from its Alternate Source through the Static Transfer Switch.

C. Loads on Unit B are supplied from the UPS battery though the Inverter.

D. Loads on Unit B are supplied from its Alternate Source through the Static Transfer Switch.

Answer: A Answer Explanation:

Power has not been restored to the UPS A primary power supply (72M), this would result in UPS A to be powered through the UPS B rectifier from 72 R.

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EXAMINATION 2012 ILO Exam - RO Question 48 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26977 User-Defined ID: R48 Cross Reference 213-0128-000-A007-004 Number:

Topic: Power to UPS A after casualty Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because power is available through UPS B by way of the rectifier.

C. is incorrect because when AC power is available it will provide the source of power.

D. is incorrect because unit B primary power supply is available.

Reference:

23.308.01 Enclosure C Question 48 Table-Item Links Plant Procedures 23.308.01 NUREG 1123 KA Catalog Rev. 2 262002 K6.01 2.7/2.9 A.C. electrical power Associated objective(s):

Describe how the Uninterruptible Power Supply System provides redundancy.

ILO EXAM Page: 110 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 49 ID: R49 Points: 1.00 When a 130V ESF Battery Charger is placed in "Equalize Mode", which one of the following occurs?

A. The battery charging rate will be decreased.

B. The Battery Charger will pick up 50% of the DC load.

C. The associated DC Bus voltage will be increased.

D. The Battery Charger voltage will equalize with the battery voltage.

Answer: C Answer Explanation:

With the battery placed in the Equalize Mode, an increase in voltage and current should be verified on the charger front panel.

ILO EXAM Page: 111 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 49 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 26958 User-Defined ID: R49 Cross Reference 315-0264-000-0002-019 Number:

Topic: Equlize Mode Operation Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because placing the charger in Equalize Mode will increase the charging rate.

B. is incorrect because the charger would pick up all the associated DC load.

D. is incorrect because this is a misconception regarding Equalize Mode.

Reference:

23.309, page 12 Question 49 Table-Item Links Plant Procedures 23.309 NUREG 1123 KA Catalog Rev. 2 263000 A1.01 2.5/2.8 Battery charging/discharging rate Associated objective(s):

Describe general DC Electrical Distribution System operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 112 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 50 ID: R50 Points: 1.00 Concurrent with a Loss of 345 kV power, Bus 65E Breakers E6 and E8 indicate TRIPPED.

What is the status of Emergency Diesel Generators (EDGs), and what action is required?

A. Only ONE Emergency Diesel Generator has started. Action should be taken to clear a Bus 65E lockout condition prior to energizing Bus 65E.

B. Only TWO Emergency Diesel Generators started. Action should be taken to manually load the EDG to re-energize Bus 65E.

C. Only THREE Emergency Diesel Generators started. Action should be taken to clear a Bus 65E lockout condition prior to energizing Bus 65E.

D. All FOUR Emergency Diesel Generators started. Action should be taken to manually load one of the EDGs to re-energize Bus 65E.

Answer: A Answer Explanation:

Bus 65E Lockout conditions are indicated by TRIP of Breakers E6 and E8. This opens the 1MY86 contact thus preventing the emergency start signal for the associated EDG. The Lockout must be cleared prior starting the EDG ILO EXAM Page: 113 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 50 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26979 User-Defined ID: R50 Cross Reference 315-0065-000-0014-002 Number:

Topic: Loss 345 kv bus lockout Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because EDG 13 will not auto start with a Lockout inhibiting the start function.

C. is incorrect because Division 1 EDGs will not receive a start signal for a loss of DIV 2 AC power.

D. is incorrect because Division 1 EDGs will not receive a start signal for a loss of DIV 2 AC power.

Reference:

10D32 Question 50 Table-Item Links Plant Procedures 10D32 NUREG 1123 KA Catalog Rev. 2 264000 A2.09 3.7/4.1 Loss of A.C. power Associated objective(s):

Given various system operating parameters, relate system/equipment operation to fundamental concepts to determine proper operation/response as described in the BWR Fundamentals Catalog.

ILO EXAM Page: 114 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 51 ID: R51 Points: 1.00 At 08:00 with the plant operating at 80% power, the EDG 11 diesel fuel oil tank develops a leak. After isolation, the fuel oil storage tank is at 24,500 gallons. Which ONE, if any, of the following Technical Specifications must be completed?

A. Perform SR 3.8.1.1 "Verify correct breaker alignment and indicated power availability for each offsite circuit" by 08:50.

B. Perform SR 3.8.1.1 "Verify correct breaker alignment and indicated power availability for each offsite circuit" by 09:15.

C. No Technical Specification actions required.

D. Be in Mode 3 by 20:00.

Answer: A Answer Explanation:

A 7 day fuel oil level of <30,240 gallons would require entry into TS 3.8.3 Condition D and required the EDG to be declared inoperable immediately. This requires entry into TS 3.8.1 Condition A which requires the performance of SR 3.8.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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EXAMINATION 2012 ILO Exam - RO Question 51 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26980 User-Defined ID: R51 Cross Reference 804-0001-000-0007-009(M)

Number:

Topic: Low fuel oil storage tank level Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because no 1.25 extensions are permitted in initial period.

C. is incorrect because 24,500 is less than the 30,240 gallon limit D. is incorrect because this action is required if associated completion time is not met.

Reference:

Tech Spec 3.8.3 Question 51 Table-Item Links NUREG 1123 KA Catalog Rev. 2 264000 K1.05 3.2/3.3 Emergency generator fuel oil supply system G2.2.39 3.9/4.5 Knowledge of less than one hour technical specification action statements for systems Technical Specifications 3.8.1 AC Sources Operating 3.8.3 Diesel Fuel Oil, and Starting Air ILO EXAM Page: 116 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Identify Emergency Diesel Generator System related technical specifications, with emphasis on action statements requiring prompt actions (for example, one hour or less).

ILO EXAM Page: 117 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 52 ID: R52 Points: 1.00 The plant is operating at 100% power with the West Station Air Compressor running, and the East Station Air Compressor in AUTO. How would the Station Air System respond if TBCCW cooling capabilities have degraded?

A. The West Station Air Compressor will trip on high air temperature and the East Compressor will auto start once air header pressure is <95 psig and run until it trips on high air temperature.

B. The West Station Air Compressor will trip on high air temperature and the East Compressor will auto start once air header pressure is <95 psig and run.

C. The West Station Air Compressor will trip on high air temperature and the East Compressor will auto start once air header pressure is <90 psig and run.

D. The West Station Air Compressor will trip on high air temperature and the East Compressor will auto start immediately and run until it trips on high air temperature.

Answer: B Answer Explanation:

With TBCCW cooling capabilities degraded, the discharge air temperature of the compressor will cause it to trip at 125°F. Once air header pressure lowers to 95 psig, the East will auto start and continue to run. The East compressor does not have a high air temperature trip.

ILO EXAM Page: 118 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 52 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26959 User-Defined ID: R52 Cross Reference NEW Number:

Topic: Degraded TBCCW flow affect Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 4 Text Field: 2012 ILO Exam Comments: .

Justification:

A. is incorrect because the East will not trip on high air temperature.

C. is incorrect because the East will auto start at <95 psig.

D. is incorrect because the East will not auto start until air header pressure lowers to <95 psig and will not trip on high air temp.

Reference:

7D61, 23.129 Enclosure A Question 52 Table-Item Links Plant Procedures 23.129 07D61 NUREG 1123 KA Catalog Rev. 2 300000 A3.02 2.9/2.7 Air temperature Associated objective(s):

Describe how the Compressed Air System provides redundancy.

ILO EXAM Page: 119 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 53 ID: R53 Points: 1.00 The plant is operating normally at 100% power when the following occurs:

480 VAC Bus 72N is deenergized.

5D5, TBCCW PUMPS DIFFERENTIAL PRESSURE HIGH/LOW Alarms.

TBCCW Headers Pressure Indicator on P43-R805 reads 17 psid.

TBCCW Pump Suction Pressure is 10 psig.

As a result of this transient, which of the following describes the status of the TBCCW system?

A. One TBCCW pump remains in service; TBCCW DP Control Valve, P43-F405 will SHUT.

B. One TBCCW pump remains in service; TBCCW DP Control Valve, P43-F405 will OPEN.

C. The operating TBCCW pump will trip on Low Suction Pressure; TBCCW DP Control Valve, P43-F405 will SHUT.

D. An additional TBCCW pump can be started; TBCCW DP Control Valve, P43-F405 will control pressure in the normal band.

Answer: A Answer Explanation:

With a loss of 480 VAC Bus 72N, two of the three TBCCW pumps are de-energized and the DP control valve will close to ensure maximum flow to components is available.

ILO EXAM Page: 120 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 53 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26960 User-Defined ID: R53 Cross Reference 202-0901-000-A001-039 Number:

Topic: Loss of 72N Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 4 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because it would be true if Differential Pressure were >30 psid C. is incorrect because it would be true if Suction Pressure were < 7 psig D. is incorrect because it would be true if Bus 72 M was deenergized and 72 N were energized

Reference:

5D5 Question 53 Table-Item Links Plant Procedures 05D005 NUREG 1123 KA Catalog Rev. 2 400000 A4.01 3.1/3 CCW indications and control Associated objective(s):

Describe how the Turbine Building Closed Cooling Water System provides redundancy.

ILO EXAM Page: 121 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 54 ID: R54 Points: 1.00 A drifting control rod can be prevented from continuing to drift out only by manually applying an insert signal. The Reactor Operator could determine that a stuck collet piston was causing this malfunction, by which of the following methods:

A. Insert the control rod one notch at a time and observe the rod remains at a given position.

B. Fully withdraw the rod with the NOTCH OVERRIDE switch, then observe the rod commence to slowly drift inward.

C. Electrically disarm the directional control valves, manually close C 11-F113 (Charging Water Isol Valve) and observe the rod stops drifting.

D. Manually close C11-F103 (Drive Water Isol Valve) and C11-F105 (Exhaust Water Isol Valve) and observe the rod commence to drift out.

Answer: D Answer Explanation:

By closing the F103 and the F105, the drive water and exhaust water are isolated.

This would eliminate the force on the under and over piston areas and confirm the collet is stuck.

ILO EXAM Page: 122 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 54 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26962 User-Defined ID: R54 Cross Reference 202-0301-000-0202-004 Number:

Topic: Determine if stuck collet piston Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 2 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because a stuck collet would cause the rod to continue to drift.

B. is incorrect because the CR should be fully inserted for a drifting rod.

C. is incorrect because, the above actions would not prevent the CR from continuing to drift from a stuck collet.

Reference:

20.106.07, note 3 Question 54 Table-Item Links Plant Procedures 20.106.07 NUREG 1123 KA Catalog Rev. 2 201003 A2.03 3.4/3.7 Drifting rod G2.1.30 4.4/4.0 Ability to locate and operate components, including local controls ILO EXAM Page: 123 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Discuss potential modes of Control Rod Drive Mechanism component failures and any industry operating experience related to the failure.

ILO EXAM Page: 124 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 55 ID: R55 Points: 1.00 The plant was operating at 100% power when the reactor scrammed due to a Group 1 isolation caused by a fault in the NSSSS logic.

NO operator action has been taken at this time. Plant conditions are as follows:

RPV level is 140" and steady ( lowest level indicated was 135").

RPV pressure is cycling between approximately 905 and 1017 psig.

What is the status of the Reactor Recirc Pump Breakers?

A. ONLY the Field Breakers are OPEN.

B. The Motor and Field Breakers are OPEN.

C. ONLY the Field Breakers are CLOSED.

D. The Motor and Field Breakers are CLOSED.

Answer: B Answer Explanation:

During a MSIV closure event, reactor pressure will reach the ATWS-ARI/RPT trip setpoint of 1133 psig. The cycling of reactor pressure between 905 and 1017 psig indicates that the SRV lift setpoint has been reached.

ILO EXAM Page: 125 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 55 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26963 User-Defined ID: R55 Cross Reference 315-0104-000-0006-010 Number:

Topic: Hi Reactor Pressure affect on RRMG Breakers Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because ARI will trip both the MG set and field breaker.

C. is incorrect because ARI will trip both the MG set and field breaker.

D. is incorrect because ARI will trip the MG sets and the field breakers.

References:

3D25; 3D26 Question 55 Table-Item Links Plant Procedures 03D025 03D026 NUREG 1123 KA Catalog Rev. 2 202001 K4.07 2.8/2.9 Motor generator set trips: Plant-Specific Associated objective(s):

List the automatic features of Reactor Recirculation system operations.

ILO EXAM Page: 126 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 56 ID: R56 Points: 1.00 Which one of the following describes the correct flow path during normal operation of the RWCU system?

A. Reactor Recirculation Loops, RWCU pumps, RHX, NRHX, Filter/Demin, Blowdown Control Valve, Main Condenser.

B. Reactor Recirculation Loops and Bottom Head Drain, RWCU pumps, NRHX, RHX, Filter/Demin, RHX, "B" feed water line C. Reactor Recirculation Loops, RWCU pumps, RHX, NRHX, Filter/Demin, RHX, "A" feed water line D. Reactor Recirculation Loops and Bottom Head Drain, RWCU pumps, RHX, NRHX, Filter/Demin, RHX, "B" feedwater line Answer: D Answer Explanation:

This is the correct flowpath.

ILO EXAM Page: 127 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 56 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26982 User-Defined ID: R56 Cross Reference 315-0108-000-B003-002(M)

Number:

Topic: RWCU Flowpath Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this is the flowpath for blowdown opeartion.

B. is incorrect because NRHX and RHX are out of order.

C. is incorrect because RWCU does not go to "A" feed line.

Reference:

23.707, page 2 Question 56 Table-Item Links Plant Procedures 23.707 NUREG 1123 KA Catalog Rev. 2 204000 K1.03 3.1/3.1 Reactor feedwater system Associated objective(s):

Draw a basic block diagram of the Reactor Water Cleanup system.

ILO EXAM Page: 128 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 57 ID: R57 Points: 1.00 During the approach to criticality, a loss of UPS A circuit 8 occurs. Which of the following statements correctly describes the response of the Rod Worth Minimizer (RWM) to this event?

A. A rod block is applied by the RWM. The WHITE "Selected Rod" light on the 4-Rod Display is NOT illuminated and the "Rod Out Perm" light is NOT illuminated.

B. A rod block is applied by the RWM. The WHITE "Selected Rod" light on the 4-Rod Display and "Rod Out Perm" is illuminated.

C. A rod block is NOT applied by the RWM. The Full Core Display Selected Rod Identification Light is NOT illuminated.

D. A rod block is NOT applied by the RWM. The Full Core Display Selected Rod Identification Light is illuminated.

Answer: A Answer Explanation:

RPIS power is supplied from UPS A circuit 8. RPIS senses Rod position and supplies this information to the RWM, the Four Rod Display and the Full Core status. The RWM will enforce a rod block if rod position is unknown.

ILO EXAM Page: 129 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 57 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 4.00 System ID: 26964 User-Defined ID: R57 Cross Reference 315-0111-000-0010-002 Number:

Topic: Loss of UPS A Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because loss of power to RPIS will cause loss of indication to the 4-rod display.

C. is incorrect because a Rod block will be generated by the RWM due to loss of RPIS.

D. is incorrect because a Rod block will be generated by the RWM due to loss of RPIS.

Reference:

23.623, section 1.1.4 Question 57 Table-Item Links Plant Procedures 23.623 NUREG 1123 KA Catalog Rev. 2 214000 K3.01 3/3.2 RWM: Plant-Specific Associated objective(s):

Discuss potential modes of Rod Worth Minimizer system component failures and any industry operating experience related to the failure.

ILO EXAM Page: 130 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 58 ID: R58 Points: 1.00 The reactor is at 54% power, 58% core flow, both recirculation pumps are in service and control rods are being withdrawn to increase power.

Control Rod 22-07 is selected. Due to a failure in RMCS, Control Rod 22-15 is also selected.

Based on these conditions, a control rod block:

A. will occur only if power exceeds 107.2%. RBM local power B. is immediately imposed by the RBM to prevent any rod movement.

C. is imposed by the RMCS once rod movement is initiated.

D. is imposed by the RWM once rod movement in initiated.

Answer: B Answer Explanation:

The RBM will initiate a Rod Block if multiple rods are selected.

ILO EXAM Page: 131 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 58 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26965 User-Defined ID: R58 Cross Reference 315-0126-000-0003-017 Number:

Topic: Failure of RMCS causing 2 rod selected Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 6 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this is the upscale setpoint for reactor power >82%

C. is incorrect because there is a failure of the RMCS and the RCMS does not enforce a Rod Block.

D. is incorrect because the RWM enforces a Rod Block at Reactor power <27% power.

Reference:

3D113 Question 58 Table-Item Links Plant Procedures 03D113 NUREG 1123 KA Catalog Rev. 2 215002 K1.06 3/3.1 Control rod selection: BWR-3,4,5 Associated objective(s):

Discuss failure modes of Reactor Manual Control System controls and vital instruments, including design features that could result in erroneous operation or indication.

ILO EXAM Page: 132 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 59 ID: R59 Points: 1.00 The plant is in Mode 5 with refueling in progress. The following conditions are present:

Fuel Pool Temperature is 108°F.

Fuel Pool Water Level is 20'2" above fuel assemblies.

FPCCU Skimmer Surge Tank Level is 3.5 feet.

Which of the following alarms, IF ANY, would be received based solely on the given information?

A. No alarms expected.

B. 2D13 FUEL POOL COOLING TROUBLE, 2D1 FUEL POOL WATER LOW C. 2D9 FUEL POOL SYSTEM TEMPERATURE HIGH, 2D13 FUEL POOL COOLING TROUBLE D. 2D1 FUEL POOL WATER LOW, 2D9 FUEL POOL SYSTEM TEMPERATURE HIGH Answer: B Answer Explanation:

You have exceeded the setpoint for 2D1, FUEL POOL WATER LOW, AND have a low skimmer surge tank level, giving you 2D13, FUEL POOL COOLING TROUBLE.

ILO EXAM Page: 133 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 59 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26983 User-Defined ID: R59 Cross Reference NEW Number:

Topic: Fuel pool low level Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 6 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because you have exceeded the setpoint for 2D1, FUEL POOL WATER LOW, and 2D13, FUEL POOL COOLING TROUBLE C. is incorrect because you have not exceeded 125°F.

D. is incorrect because you have not exceeded 125°F.

References:

2D1; 2D13 Question 59 Table-Item Links Plant Procedures 02D013 02D001 03D113 NUREG 1123 KA Catalog Rev. 2 233000 A4.04 2.9*/3.1 Pool level Technical Specifications 3.7.7 Spent Fuel Storage Pool Water Level ILO EXAM Page: 134 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Identify alarm response procedures associated with the Fuel Pool Cooling and Cleanup System.

ILO EXAM Page: 135 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 60 ID: R60 Points: 1.00 Off Gas Hydrogen concentration has increased to 2.0% with the East Recombiner train in service. Which of the following conditions could cause this condition?

A. N20-F403, Cond Byp Line FCV, fails open.

B. N20-F403, Cond Byp Line FCV, fails closed.

C. N62-F400, 18"Manifold Steam Supply TCV, fails closed.

D. N62-F401A, MS To East Prehtr TCV, fails closed.

Answer: D Answer Explanation:

The Preheater increases the Off Gas temperature from 350°F to 380°F and superheats the water vapor to improve the efficiency of the recombiner catalyst. If this valve failed closed, it would decrease the efficiency of the recombiner, therefore increasing the Hydrogen concentration.

ILO EXAM Page: 136 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 60 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 27158 User-Defined ID: R60 Cross Reference 315-0135-000-0004-003 Number:

Topic: Off Gas-Hydrogen Recombiner Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 4 Text Field: 2012 ILO EXAM Comments: Justification:

A. is incorrect because this would have no effect on Hydrogen concentration.

B. is incorrect because this would have no effect on Hydrogen concentration.

C. is incorrect because this would decrease Hydrogen concentration.

Reference:

6D25 Question 60 Table-Item Links Plant Procedures 06D25 NUREG 1123 KA Catalog Rev. 2 239001 K3.04 2.8/2.8 Offgas system Associated objective(s):

Given Off Gas System performance data, detect abnormalities, and determine possible causes for performance problems.

ILO EXAM Page: 137 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 61 ID: R61 Points: 1.00 The main generator has been operating with the following conditions for the last 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months s:

Generator voltage: 120.5

Generator VARs: 50 MVAR lag

Generator Output: 840 MWe Using Enclosure C of 23.118 (graph below), how much block load may be removed from the machine?

)E WADI NG RATE AFTER REMOVAL OF 15.] ..E*R

.Z.! \ ACV ..'..1 BLOCK LOAD = 13 MW /MIN OF 81_0(:. LOAF:

a 5 MW/MIN 600 =pp:

MAX BLOCK LOAD THAI . WWI CAN :ll. N.F.MOVE1") \\ .'

jksl *11:.

LOAD la

,. . . . 1.

.E.H.F5E . RAT..; APPLY IF 111-I L .`..-'. AC: [E NT [*. TO CONTINUE OPERATING Al 113E NEW LOWFER LOAD

. ..4.

1 .. ,

it

lil 2' ) :i0 :) 60 12:1 240 :ifs;' 6C.00 77a $W, 961.: 1 MACHINE LOAD A. 420 MWe B. 40% of rated MWe C. 13 MW/MIN D. 600 MWe Answer: A Answer Explanation:

Following the chart on enclosure C would indicate the maximum block load removal for the above conditions would be 420 MWe.

ILO EXAM Page: 138 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 61 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26966 User-Defined ID: R61 Cross Reference 315-0155-000-0005-003(M)

Number:

Topic: How much block load can be removed Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because 40% of rated load would exceed the maximum line C. is incorrect because the 13MW/MIN is applied after the initial load is removed D. is incorrect because this would exceed the maximum load reduction.

Reference:

23.118 Enclosure C Question 61 Table-Item Links Plant Procedures 23.118 NUREG 1123 KA Catalog Rev. 2 245000 K5.07 2.6/2.9 Generator operations and limitations Associated objective(s):

Identify relationships between significant Main Generator and Excitation System operating parameter values.

ILO EXAM Page: 139 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 62 ID: R62 Points: 1.00 The plant is operating at 100% power when an electrical fault trips the NORMAL feed to 65D. What is the impact on the Condensate system?

A. A decrease of Condensate will cause a low suction pressure trip of the Heater Feed Pumps and Reactor Feedwater Pumps.

B. A decrease of Condensate will cause a loss of cooling to the Reactor Feedwater pump bearings.

C. A decrease in Condensate will cause a loss of Heater Drains and a Reactor Recirc runback to Limiter 3.

D. A decrease in Condensate will cause a reduction in feedwater heating and subsequent Reactor power spike.

Answer: A Answer Explanation:

The loss of 65D will cause a trip of the North and South Condenser pumps and loss of feedwater to the vessel. This will require entry into 20.107.01 Loss of Feedwater or Feedwater Control, and the immediate action of placing the mode switch in shutdown ILO EXAM Page: 140 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 62 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26967 User-Defined ID: R62 Cross Reference NEW Number:

Topic: Effect of loss of condensate Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because a loss of condensate will result in a RFP trip and SCRAM condition.

C. is incorrect because a loss of condensate will result in a RFP trip and SCRAM condition.

D. is incorrect because a loss of condensate will result in a RFP trip and SCRAM condition.

Reference:

20.300.65D Attachment 1 Question 62 Table-Item Links Plant Procedures 20.107.01 20.300.65D NUREG 1123 KA Catalog Rev. 2 256000 K2.01 2.7*/2.8 System pumps Associated objective(s):

Discuss the Condensate system interrelationships with other systems.

ILO EXAM Page: 141 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 63 ID: R63 Points: 1.00 During a startup, the North RFPT is operating.

The following conditions exist:

Reactor Power is 1% CTP.

Reactor pressure is 650 psig.

SULCV is 40% open.

SULCV WA Station is in AUTO.

North Feedwater Flow Control WA Station is in MANUAL.

The Interruptible Air Supply to the SULCV is lost.

(1) How will this failure FIRST affect RPV Water Level? AND (2) What actions will mitigate this failure?

A. (1) RPV Water Level will RISE.

(2) Manually close the SULCV locally.

B. (1) RPV Water Level will RISE.

(2) Trip the North RFPT, start the West Standby Feedwater Pump and control RPV Water Level using N2103-F003, SBFW 4" Disch Flow Ctrl Vlv.

C. (1) RPV Water Level will LOWER.

(2) Start the West Standby Feedwater Pump and control RPV Water Level using N2103-F003, SBFW 4" Disch Flow Ctrl Vlv.

D. (1) RPV Water Level will LOWER.

(2) Place the Feedwater Flow Control WA Station in AUTO and open N2100-F607, N RFP Disch Line Iso Valve.

Answer: B Answer Explanation:

SULCV fails open on a loss of air. With Reactor Feed Pump in manual, RPV Water level will rise. Tripping the RFPT will stop flow through the SULCV and SBFW can be used to control level.

ILO EXAM Page: 142 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 63 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 27059 User-Defined ID: R63 Cross Reference 315-0146-000-B006-001 Number:

Topic: Loss of IAS to SULCV Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because you have lost the mode of force for activating SULCV.

C. is incorrect because level will rise.

D. is incorrect because level will rise.

Reference:

20.129.01, page 2 Question 63 Table-Item Links Plant Procedures 20.129.01 23.107 NUREG 1123 KA Catalog Rev. 2 259001 A2.07 3.7/3.8 Reactor water level control system malfunctions Associated objective(s):

Discuss potential modes of Feedwater Control System component failures and any industry operating experience related to the failure.

ILO EXAM Page: 143 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 64 ID: R64 Points: 1.00 The plant is operating at 100%, an electrical fault causes a loss of bus 69K. Which one of the following describes the effect on the Fire Protection System?

A. The Jockey Pump will de-energize. The Electric Fire pump will start when Fire Main Pressure decreases to 110 psig.

B. The Jockey Pump will de-energize. The Electric Fire pump will start when Fire Main Pressure decreases to 130 psig.

C. The Jockey Pump and Electric Fire pump will be de-energized. The Diesel Fire Pump will start when Fire Main Pressure decreases to 110 psig.

D. The Jockey Pump and Electric Fire pump will be de-energized. The Diesel Fire Pump will start when Fire Main Pressure decreases to 130 psig.

Answer: B Answer Explanation:

Loss of 120kv de-energizes 68K AND 72K, the power supplies to the Jockey Pump and Electric Fire Pump. The Diesel Pump will auto start when pressure drops below 110 psig.

ILO EXAM Page: 144 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 64 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26968 User-Defined ID: R64 Cross Reference NEW Number:

Topic: Loss of 120KV effect Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because Electric fire pump starts at 130 psig.

C. is incorrect because Electric Fire Pump has power.

D. is incorrect because Diesel Fire Pump starts at 110psig and the Electric Fire Pump has power.

Reference:

7D6 Question 64 Table-Item Links Plant Procedures 07D06 20.300.69K NUREG 1123 KA Catalog Rev. 2 286000 K6.01 3.1/3.1 A.C. electrical distribution: Plant-Specific Associated objective(s):

Describe how the Fire Protection and Detection System provides redundancy.

ILO EXAM Page: 145 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 65 ID: R65 Points: 1.00 The reactor is operating in Mode 2 at 5% power. The P603 Operator is pulling control rods to increase power when the following is observed:

3D76 CONTROL ROD OVERTRAVEL

3D80 CONTROL ROD DRIFT

All APRMs indicate a rise in power

Dl1-R603 Main Steam Line PRMS Recorder indicates a rise in levels Which of the following would describe (1) the impact on the plant, and (2) what action should be taken?

A. 1) A control rod is drifting out of the core causing power to increase.

2) Select the drifting rod and insert to the original position per 20.106.07 "Control Rod Drift".

B. 1) A control rod has dropped with possible fuel failure.

2) Attempt to re-couple rod per 20.106.02 "Uncoupled / Dropped Control Rod".

C. 1) Reactor will scram on APRM setdown.

2) Place Mode switch in shutdown and perform actions 20.000.21 "Reactor Scram".

D. 1) A control rod has drifted out of the core with possible fuel failure.

2) Immediately insert and disarm the Control Rod in accordance with 20.106.07 "Control Rod Drift".

Answer: B Answer Explanation:

The symptoms indicate that a control rod has dropped from the core and an increase in activity is occurring from the dropped rod.

ILO EXAM Page: 146 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 65 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26970 User-Defined ID: R65 Cross Reference 802-2004-000-0005-007(M)

Number:

Topic: Control rod drop Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because the alarms indicate that a control rod has dropped from the core.

C. is incorrect because reactor power will not reach the 15% upscale trip.

D. is incorrect because you would first try to re-couple the rod..

Reference:

20.106.02, page 3 Question 65 Table-Item Links Plant Procedures 03D076 20.106.02 NUREG 1123 KA Catalog Rev. 2 290002 A2.03 3.6/3.9 Control rod drop accident Associated objective(s):

Given Control Rod Drive Hydraulic system performance data, detect abnormalities, and determine possible causes for performance problems.

ILO EXAM Page: 147 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 66 ID: R66 Points: 1.00 During an ATWS, SLC Pump B has been started. The following indications are observed:

RPV Pressure is 1015 psig.

SLC Tank Level is 72 inches decreasing.

SLC Pump Discharge Pressure is 1050 psig.

3D11, SLC IGNITION CONTINUITY LOSS, is activated.

BOTH H11P603 Continuity Circuit indicating lights are OFF.

RWCU G3352-F004 and F220 both CLOSED.

RWCU G3352-F001 remains OPEN.

The above conditions indicate which of the following?

A. Normal operation.

B. SLC Explosive Valves failed to fire.

C. RWCU failed to isolate on SLC injection.

D. SLC Pump B Discharge Relief Valve failed open.

Answer: A Answer Explanation:

Proper indication of SLC injection include RWCU isolation (G3352-F004 and F220 only), SLC tank level decreasing, 3D11 activated, Continuity Circuit indicating lights off, and pressure slightly higher than RPV pressure.

ILO EXAM Page: 148 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 66 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26984 User-Defined ID: R66 Cross Reference 2011 LOR EXAM Number:

Topic: SLC Normal operation Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because if they failed to fire, 3D11 would not alarm, Continuity Circuit indicating lights would be on, and pressure would be higher.

C. is incorrect because RWCU did isolate properly, but there is a common misconception G3352-F001 shuts on SLC injection.

D. is incorrect because even though pressure is higher, it is not fluctuating as indication of relief valve stuck open.

Reference:

23.139, page 11 Question 66 Table-Item Links Plant Procedures 23.139 NUREG 1123 KA Catalog Rev. 2 G2.1.31 4.6/4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup ILO EXAM Page: 149 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

State the normal values of significant Standby Liquid Control System parameters.

ILO EXAM Page: 150 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 67 ID: R67 Points: 1.00 There is a small leak in the Steam Tunnel. Using a camera, an isolation valve has been identified. During the pre job brief, this activity is identified as MODERATE. RP determines double PCs are required for entry. Dry Bulb temperature is 103°F, and no other heat stress prevention equipment will be used.

After isolating the leak, the Nuclear Operator reports the job took 10 minutes. When is the EARLIEST you can send this Nuclear Operator back to normal duties? (See attached SAFETY HANDBOOK, Ch 21)

A. After 10 minutes of rest time.

B. After 20 minutes of rest time.

C. After 30 minutes of rest time.

D. After 60 minutes of rest time.

Answer: C Answer Explanation:

Using TABLE 21-2A, stay time is 20 minutes for double PCs for a temperature of 103°F. Using the rest time calculation on page 21.5, rest time is 30 minutes.

ILO EXAM Page: 151 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 67 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 27118 User-Defined ID: R67 Cross Reference NEW Number:

Topic: Heat Stress Actions Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect, but could be correct if chart read wrong or calculation not properly utilized.

B. is incorrect because This is the actual stay time allowed.

D. is incorrect because if this does not take the ratio of time worked vs stay time into the calculation.

Reference:

Safety Handbook, Section 21, Table 21-2A Question 67 Table-Item Links Plant Procedures Safety Handbook, Section 21, Hot and Cold Environments / Temperature Extremes NUREG 1123 KA Catalog Rev. 2 G2.1.26 3.4/3.6 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

ILO EXAM Page: 152 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen) (CFR: 41.10 / 45.12) RO 3.4 SRO 3.6 ILO EXAM Page: 153 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 68 ID: R68 Points: 1.00 Per 23.138.01, Reactor Recirculation System, which ONE of the following describes the minimum qualification and coordination requirements for local operation of a Recirculation MG Set Scoop Tube?

A. A qualified Nuclear Operator in communication with the Main Control Room can perform scoop tube position adjustment.

B. A licensed Nuclear Supervising Operator in communication with the Main Control Room can perform scoop tube position adjustment.

C. A qualified Nuclear Operator can perform scoop tube position adjustment with a licensed Nuclear Supervising Operator supervising at the Recirculation MG Set.

D. A licensed Nuclear Supervising Operator can perform scoop tube position adjustment with a Senior Reactor Operator supervising at the Recirculation MG Set.

Answer: B Answer Explanation:

Per 23.138.01, a licensed operator can perform local scoop tube position adjustment while in constant communication with the Control Room Operator.

ILO EXAM Page: 154 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 68 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 26998 User-Defined ID: R68 Cross Reference 315-0104-000-0001-001 Number:

Topic: Qualifications for scoop tube adjuctment Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect although NOs do operate equipment outside the Main Control Room.

C. is incorrect although NOs do operate equipment outside the Main Control Room.

D. is incorrect because you have to be in constant communication with the Control Room Operator.

Reference:

23.138.01, page 18 Question 68 Table-Item Links Plant Procedures 23.138.01 NUREG 1123 KA Catalog Rev. 2 G2.1.8 3.4/4.1 Ability to coordinate personnel activities outside the control room ILO EXAM Page: 155 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Describe methods for monitoring plant status, control of equipment, and maintaining proper Control Room work environment, including:

a. The responsibility of the CRNSO.

b. The five CRNSO Guidelines to ensure continued monitoring of plant status.

c. Access to the Control Room and exceptions to the access requirements.

d. Leaving the "At Controls Area."

e. Removing a system/component from service.

f. Restoring a system/component to service.

g. Performing valve, electrical, and instrument lineups.

ILO EXAM Page: 156 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 69 ID: R69 Points: 1.00 While testing Source Range Monitors (SRMs) prior to startup, the following SRM status is noted:

Channel SRM Detectors Inserted Signal to Noise Ratio A 3 counts per second 18 B 2 counts per second 18 C 2 counts per second 22 D 2 counts per second 21 Which one of the following describes the status of Source Range Monitors?

A. ONE SRM is NOT capable of supporting a Reactor Startup.

B. TWO SRMs are NOT capable of supporting a Reactor Startup.

C. THREE SRMs are NOT capable of supporting a Reactor Startup.

D. ALL SRMs are capable of supporting a Reactor Startup.

Answer: A Answer Explanation:

SRM B has <3cps AND S/N ratio below 20.

ILO EXAM Page: 157 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 69 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 4.00 System ID: 26999 User-Defined ID: R69 Cross Reference 315-0022-000-A017-001 Number:

Topic: SRM Operability Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

B/C/D are incorrect because only SRM B has <3cps AND S/N ratio below 20.

Reference:

Tech Spec 3.3.1.2 Question 69 Table-Item Links Plant Procedures 22.000.01 23.602 NUREG 1123 KA Catalog Rev. 2 G2.2.1 4.5/4.4 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity Technical Specifications 3.3.1.2 Source Range Monitor (SRM) Instrumentation ILO EXAM Page: 158 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Describe the Power Range Neutron Monitoring System technical specification limiting conditions for operation, their bases, the associated surveillance requirement(s), and their relationship to operability.

ILO EXAM Page: 159 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 70 ID: R70 Points: 1.00 Per MOP05, Control of Equipment, "Access to Protected Areas may be granted to allow activities deemed necessary by the Shift Manager." Which of the following personnel are NOT exempt from Protected Equipment restrictions?

A. Security B. Plant Manager C. NRC inspectors D. Nuclear Operators Answer: B Answer Explanation:

Per MOP 5, Control of Equipment, Security, Operations, and NRC inspectors are exempt from Protected Equipment restrictions.

Question 70 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 27062 User-Defined ID: R70 Cross Reference NEW Number:

Topic: Protected Equipment Posting exemptions Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A/C/D are all exempt.

Reference:

MOP05, pages 30 & 31 ILO EXAM Page: 160 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 70 Table-Item Links Plant Procedures MOP05 - Control Of Equipment NUREG 1123 KA Catalog Rev. 2 G2.2.14 3.9/4.3 Knowledge of the process for controlling equipment configuration or status Associated objective(s):

List and describe other "systems" that assist Operations in the control of equipment and tracking of information in the plant, including:

a. Shiftly Responsibilities

b. Audits

c. Evolution Evaluation Program

d. Control Room Information System

e. Deleted

f. Night Orders

g. Operations Department Instructions

h. Limiting Condition for Operation ILO EXAM Page: 161 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 71 ID: R71 Points: 1.00 The plant is operating at full power.

The following Drywell Floor and Equipment Drain Sump Effluent Integrator readings (total gallons pumped) have been noted for the past 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

TIME Floor Drain Equipment Drain Leak Rate Leak Rate Integrator Integrator Floor (gpm) Equipment (gpm) 0000 89321 27861 2.3 16.4 0800 90543 35805 2.54 16.55 1600 92079 44181 3.2 17.45 0000 94383 52821 4.8 18.0 With these conditions, which ONE of the following statements is correct?

A. NO Drywell Leakage limit has been exceeded.

B. TOTAL LEAKAGE has exceeded the leakage limit C. UNIDENTIFIED LEAKAGE has exceeded the leakage limit D. UNIDENTIFIED LEAKAGE INCREASE has exceeded limits within a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Answer: D Answer Explanation:

A 2 gpm increase in UNIDENTIFIED DRYWELL LEAKAGE within a twenty four hour period has been exceeded. 2.3 gpm increased to 4.8 gpm in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ILO EXAM Page: 162 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 71 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26978 User-Defined ID: R71 Cross Reference 315-0116-000-0003-015 Number:

Topic: TS Unidentified Leakage Rate Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 5 Text Field: 2012 ILO Exam Comments: Plausible Distractors:

A is plausible; would be true in MODE 2 STARTUP, because the 2 gpm increase in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is NA in MODE 2.

B is plausible; would be true if 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Total Leakage exceed 25 gpm (22.8 gpm actual).

C is plausible; would be true if 5.0 gpm Floor Leakage were exceeded (4.8 gpm max).

Reference:

Tech Spec 3.4.4 Question 71 Table-Item Links NUREG 1123 KA Catalog Rev. 2 G2.2.22 4.0/4.7 Knowledge of limiting conditions for operations and safety limits Technical Specifications 3.4.4 RCS Operational LEAKAGE ILO EXAM Page: 163 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Given plant conditions that constitute non-compliance with any LCO, apply Technical Specifications and Bases to determine the applicable Condition(s),

Required Action(s), and associated Completion Time(s).

ILO EXAM Page: 164 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 72 ID: R72 Points: 1.00 A licensed operator is conducting a normal day to day inspection of equipment which is located in a high radiation area. In accordance with plant administrative procedures, the operator must perform the inspection by which of the following methods?

A. The evolution should be preplanned and the received dose should be maintained ALARA.

B. The operator should enter the area with a hand held monitoring device.

C. Obtain Radiation Protection approval prior to the inspection.

D. Conducted by a visual inspection at the barrier to the area.

Answer: D Answer Explanation:

IAW MOPO4, Normal, day to day inspection of high radiation areas should be made by visual inspection at the door for abnormal conditions such as steam, leaks, high temperature, or unusual noises ILO EXAM Page: 165 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 72 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 27378 User-Defined ID: R72 Cross Reference 802-4101-0033-002 Number:

Topic: Radiological safety in locked high rad area Num Field 1: LOK:L Num Field 2: 10 CFR 55.41 (b) 10 Text Field: 2012 ILO Exam Comments: A. is incorrect because this necessary if it is required to enter the inspection area.

B. is incorrect because entry is not allowed for day to day inspections.

C. is incorrect because this action would be required per MRPO6 if entry was needed.

Question 72 Table-Item Links Operations Related Procedures MOPO4 Shift Operations NUREG 1123 KA Catalog Rev. 2 G2.3.12 3.2/3.7 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Associated objective(s):

Describe the requirements that must be followed while In control of a High Radiation, Locked High Radiation, or Very High Radiation Areas at Fermi 2 including storage and inventory of Fermi 1 keys ILO EXAM Page: 166 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 73 ID: R73 Points: 1.00 Which one of the following conditions will cause the Division 1 Accident Range Monitor to automatically shift from STANDBY to OPERATE?

A. Automatic start of Division 1 SGTS.

B. Automatic shift of CCHVAC to the Recirc Mode.

C. High Radiation Trip of Div 1 or 2 Containment High Range Radiation Monitors.

D. High Radiation Alarm on the Div 1 SGTS SPING Medium Range Noble Gas Channel.

Answer: D Answer Explanation:

High radiation ALARM ON THE Div 1 SGTS SPING Medium Range Noble gas channel will cause Div 1 AXM to automatically shift from standby to operate.

ILO EXAM Page: 167 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 73 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26969 User-Defined ID: R73 Cross Reference 315-0150-000-0000-001 Number:

Topic: Division 1 AXM shift to Operate Num Field 1: LOK H Num Field 2: 10 CFR 55.41 (b) 12 Text Field: 2012 ILO Exam Comments: Justification:

A/B/C are plausible; this is likely to occur during high rad conditions, but will not cause the AXM to shift from standby to operate.

Reference:

23.625 Enclosure G, page 1 Question 73 Table-Item Links Plant Procedures 23.625 NUREG 1123 KA Catalog Rev. 2 G2.3.15 2.9/3.1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Associated objective(s):

Describe general Process Radiation Monitoring System operation, including component operating sequence, normal operating parameters, and expected system response.

ILO EXAM Page: 168 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 74 ID: R74 Points: 1.00 Select the response that correctly completes the following statement concerning notifications during an RERP event.

State and Local authorities must be contacted within (1) and the NRC must be informed no later than _(2)_.

A. 1. 60 minutes

2. 60 minutes B. 1. 15 minutes

2. 15 minutes C. 1.30 minutes

2. 45 minutes D. 1. 15 minutes

2. 60 minutes Answer: D Answer Explanation:

Per EP-290, State and Local authorities must be contacted within 15 minutes and the NRC 60 minutes after classifying an event.

ILO EXAM Page: 169 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 74 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 26943 User-Defined ID: R74 Cross Reference 831-0001-000-0001-001 Number:

Topic: RERP Notification Times Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A/B/C is plausible, but do not meet the requirements of EP-290.

Reference:

EP-290, pages 3 & 5 Question 74 Table-Item Links Plant Procedures EP-290 NUREG 1123 KA Catalog Rev. 2 G2.4.43 3.2/3.8 Knowledge of emergency communications systems and techniques ILO EXAM Page: 170 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Given a reportable event, discuss the requirements and responsibilities for making notifications to Regulatory Agencies and the Company, including:

a. What events require immediate notification.

b. The relationship between the severity of the event and the NRC Notification/Reporting requirement.

c. Completely filling out a Fire Protection System Impairment Form.

d. What notifications are required if the SM or CRS authorize a departure from procedures or Technical Specifications.

e. Exclusions to required notifications to the NRC.

ILO EXAM Page: 171 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO 75 ID: R75 Points: 1.00 While operating at full power, Alarm 3D8 DIV I/II OFF GAS RADN MONITOR UPSCALE alarms. The CRNSO reports Dl1-R601 (OFF GAS LOG SCALE PRMS REC) CH AB readings are 980 mr/hr and 995 mr/hr, with both RISING. The observed off gas flow rate is currently 105 SCFM.

Using Tech Spec Offgas Radiation Monitors Conversion Factors from 78.000.09, Att. 3, what is the current Offgas Rad Release Rate and what actions, if any, are required?

A. The Tech. Spec. Offgas Rad Release Rate limit has not been exceeded.

No further actions are necessary.

B. The Tech. Spec. Offgas Rad Release Rate limit has been exceeded.

Reduce reactor power to radiation levels within the Tech Spec. limits C. The Tech. Spec. Offgas Rad Release Rate limit has not been exceeded.

Reduce reactor power to ensure that the limit is not exceeded.

D. The Tech. Spec. Offgas Rad Release Rate limit has been exceeded. Place the Mode switch in SHUTDOWN and shut the MSIVs and Main Steam Line drains.

Answer: C Answer Explanation:

The calculated release rate is approaching the TS limit of 340. Condition B of 20.000.07 requires a power reduction to prevent exceeding the TS limit ILO EXAM Page: 172 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Question 75 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 27078 User-Defined ID: R75 Cross Reference 315-0135-000-0010-001(M)

Number:

Topic: High OffGas Rad Release Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because 20.000.07 has required actions associated with an increase in Off Gas Rad levels.

B/D. is incorrect because the off gas release rates have not been exceeded.

Reference:

20.000.07, page 3 Question 75 Table-Item Links Plant Procedures 03D008 20.000.07 NUREG 1123 KA Catalog Rev. 2 G2.4.47 4.2/4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material Technical Specifications 3.7.5 Main Condenser Offgas ILO EXAM Page: 173 of 174 17 January 2012

EXAMINATION 2012 ILO Exam - RO Associated objective(s):

Recognize symptoms for entry into emergency and abnormal operating procedures.

ILO EXAM Page: 174 of 174 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 1 ID: SOl Points: 1.00 While in Mode 1 conducting SR 3.5.1.2 "functional test of LPCI swing bus automatic throwover scheme", the surveillance FAILS. (1) What is the operability status of LPCI, and (2) what action is required per Technical Specifications?

A. (1) One LPCI subsystem is INOPERABLE.

(2) Restore subsystem within 7 days.

B. (1) One LPCI pump in both subsystems is INOPERABLE.

(2) Restore pumps within 7 days.

C. (1) Two LPCI subsystems are INOPERABLE.

(2) Immediately enter LCO 3.0.3.

D. (1) Two LPCI subsystems are INOPERABLE.

(2) LCO 3.0.3 may be delayed up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Answer: C Answer Explanation:

Two LPCI subsystems are INOPERABLE and must enter LCO 3.03 immediately.

ILO EXAM Page: 1 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 4.00 System ID: 26718 User-Defined ID: SO1 Cross Reference NEW Number:

Topic: TS Operability and Action for SR 3.5.1.2 Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 2 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this is true if this surveillance only imp one subsystem.

B. is incorrect because this is true 3.5.1 condition B.

D. is incorrect because Conditions and Required Actions may be delayed up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for completion of the required testing. If it fails the test, you must immediately enter LCO 3.03.

Reference:

Tech Spec 3.5.1.2 Question 1 Table-Item Links Plant Procedures 24.321.07 NUREG 1123 KA Catalog Rev. 2 295003 AK3.01 3.3/3.5 Manual and auto bus transfer G2.2.36 3.1/4.2 Ability to analyze the effect of maintenance activities such as degraded power sources, on the status of limiting conditions for operations Technical Specifications 3.5.1 ECCS Operating ILO EXAM Page: 2 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Given plant conditions that constitute non-compliance with any LCO, apply Technical Specifications and Bases to determine the applicable Condition(s),

Required Action(s), and associated Completion Time(s).

ILO EXAM Page: 3 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 2 ID: SO2 Points: 1.00 The following conditions exist after the control room was immediatelyabandoned due to a fire in the Main Control Room:

Reactor water level at 50" and lowering

Reactor pressure cycling between 905-1017 psig

Torus water temperature at 105°F and rising

Drywell pressure at 1.1 psig and rising

UPS A & B are powered by UPS battery As the Control Room Supervisor, which action would you direct first, and what is the reason for this action?

A. Start RCIC to prevent uncovering the core.

B. Start CTG 11-1 to restore electrical power to necessary loads.

C. Start RHR Pump C in torus cooling to remove the heat from the open SRVs.

D. Start Drywell Fans 1 & 2 to prevent an unwanted high drywell pressure actuation.

Answer: B Answer Explanation:

Evacuation of the MCR due to fire in 3L zone requires entry into 20.000.18 Dedicated Shutdown Panel. The first action requires starting the CTG, which will allow for starting the Standby Feedwater to restore level.

ILO EXAM Page: 4 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26720 User-Defined ID: SO2 Cross Reference 202-1103-000-A001-005 Number:

Topic: Direct actions for Evacuation of Main Control Room Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this would be valid work direction if you were at Remote Shutdown Panel.

C. is incorrect because this would be a supplemental action with rising torus temperature.

D. is incorrect because this would be a supplemental action with rising drywell pressure.

Reference:

20.000.18, page 3 Question 2 Table-Item Links Plant Procedures 20.000.18 NUREG 1123 KA Catalog Rev. 2 295016 AA1.04 3.1/3.2 A.C. electrical distribution G2.1.7 4.4/4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation ILO EXAM Page: 5 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Direct and Monitor the shift team during performance of an emergency / abnormal operating procedures.

ILO EXAM Page: 6 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 3 ID: S03 Points: 1.00 While the plant is operating at full power, annunciator 7D50, Div I/II Control Air Compressor Auto Start alarms. The following conditions exist:

RPV Pressure is 1024 psig and stable.

RPV Water Level is 197 inches and stable.

Reactor Power is 100% and stable.

Both RR MG Sets are at 77% speed with no limiter in effect.

Station Air Header Pressure is 79 psig.

Which ONE of the following identifies the cause of the annunciator 7D50 and the required action?

A. The Control Air Compressor started on Control Air Pressure less than 85 psig. ENTER 20.129.01, Loss of Station and/or Control Air.

B. The Control Air Compressor started on Station Air Header Pressure less than 90 psig. ENTER 20.129.01, Loss of Station and/or Control Air.

C. The Control Air Compressor started on Station Air Pressure less than 80 psig. DISPATCH an operator to cross connect IAS to Div 2 NIAS per 23.129, Station and Control Air System.

D. The Control Air Compressor started on Control Air Header Pressure less than 80 psig. DISPATCH an operator to cross connect IAS to Div 2 NIAS per 23.129, Station and Control Air System.

Answer: A Answer Explanation:

The Control Air Pressure less than 85 psig is entry condition for 20.129.01, Loss of Station and/or Control Air. This also causes 7D50 to alarm.

ILO EXAM Page: 7 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26739 User-Defined ID: S03 Cross Reference 315-0071-000-0011-002 Number:

Topic: Actions required for Loss of Control Air pressure.

Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because Station Air Header does not cause the 7D50 alarm.

C. is incorrect because Station Air Header does not cause the 7D50 alarm.

D. is incorrect because you would enter 20.129.01 Loss of Station and/or Control Air.

Reference:

20.129.01, page 3 Question 3 Table-Item Links Plant Procedures 20.129.01 07D50 NUREG 1123 KA Catalog Rev. 2 295019 AA2.01 3.5/3.6 Instrument air system pressure Associated objective(s):

Direct and Monitor the shift team during performance of an emergency / abnormal operating procedures.

ILO EXAM Page: 8 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 4 ID: SO4 Points: 1.00 The plant just entered Mode 4 in preparation for a Refueling Outage. Div 1 RHR aligned for SDC. A leak develops in the RWCU system and isolates on high differential flow. The following alarms and indications are observed:

1D23, DIV I RHR PUMP A/C MOTOR TRIPPED

3D79 REAC VESSEL WATER LEVEL L3

RPV water level is 170 inches and steady.

RPV temperature is 150°F and rising slowly.

As CRS, (1) what procedure(s) would be selected to mitigate this event and (2) what actions are the minimum required to be performed to allow restoration of Div 1 RHR to Shutdown Cooling?

A. (1) 20.205.01 LOSS OF SHUTDOWN COOLING (2) Reset NSSS logic, and depress E1150-F015A Seal In Reset pushbutton.

B. (1) 20.205.01 LOSS OF SHUTDOWN COOLING, 29.100.01 SH 5 SEC CONT/RAD RELEASE (2) Reset NSSS logic, and depress E1150-F015A Seal In Reset pushbutton.

C. (1) 20.205.01 LOSS OF SHUTDOWN COOLING, 29.100.01SH 1 RPV CONTROL (2) Raise level above 220", reset NSSS logic, and depress E1150-F015A Seal In Reset pushbutton.

D. (1) 20.205.01 LOSS OF SHUTDOWN COOLING, 29.100.01SH 1 RPV CONTROL, 29.100.01 SH 5 SEC CONT/RAD RELEASE (2) Raise level above 220", reset NSSS logic, and depress E1150-F015A Seal In Reset pushbutton.

Answer: C Answer Explanation:

You are below entry conditions for sheet 5, but are in 20.205.01 and sheet 1 because of level 3. Actions are contained in condition C of 20.205.01.

ILO EXAM Page: 9 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26741 User-Defined ID: SO4 Cross Reference NEW Number:

Select appropriate EOP / AOP and direct actions for Topic:

Loss of Shutdown Cooling.

Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because you meet entry conditions for sheet 1. This directs you to raise level as does the AOP.

B. is incorrect because you do not meet entry conditions for sheet 5, you meet entry conditions for sheet 1. This directs you to raise level as does the AOP.

D. is incorrect because you do not meet entry conditions for sheet 5.

Reference:

20.205.01, page 5 Question 4 Table-Item Links Plant Procedures 20.205.01 29.100.01 SH 1 29.100.01 SH 5 NUREG 1123 KA Catalog Rev. 2 295021 AA2.03 3.5/3.6 Reactor water level ILO EXAM Page: 10 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Select the appropriate EOP / AOP based on plant conditions.

ILO EXAM Page: 11 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 5 ID: S05 Points: 1.00 The plant was shut down due to a leak in the drywell. The following conditions exist:

All rods inserted.

RPV level 150 inches and recovering with HPCI, and Standby Feedwater injecting.

Both Reactor Feed Pumps are tripped, Heater Feed Pumps are available.

RPV Pressure is 890 psig and slowly lowering.

Drywell Pressure is 9 psig and rising.

Drywell Temperature is 130°F and rising.

Torus Pressure is 7.5 psig and rising.

As CRS, you should direct which of the following?

A. Initiate Torus Cooling and Torus Sprays.

B. Isolate EECW TO and FROM the Drywell.

C. Operate all available Drywell Cooling using 29.ESP.08.

D. Lower primary pressure using turbine bypass to allow Heater Feed Pumps to recover level to 173-214 inches.

Answer: A Answer Explanation:

Per 29.100.01 SH 2, step PCP-4, you must spray the torus prior to torus pressure reaching 9 psig. The standard order is place in torus cooling /torus spray.

ILO EXAM Page: 12 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26743 User-Defined ID: SO5 Cross Reference NEW Number:

Topic: Direct action for PC Control.

Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because you have not exceeded 242°F drywell temperature. You will however isolate EECW to the drywell in step PCP-3.

C. is incorrect because you have not exceeded 145°F.

You will however operate all available drywell cooling, but not use 29.ESP.08.

D. is incorrect because with level recovering, your priority would be addressing containment. This would be a strategy if level was not recovering.

Reference:

29.100.01 SH 2, PCP-4 Question 5 Table-Item Links Plant Procedures 29.100.01 SH 2 NUREG 1123 KA Catalog Rev. 2 295024 EA2.04 3.9/3.9 Suppression chamber pressure: Plant-Specific ILO EXAM Page: 13 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Direct and Monitor the shift team during performance of an emergency / abnormal operating procedures.

ILO EXAM Page: 14 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 6 ID: S06 Points: 1.00 With the plant operating at 100% power, the following occur:

8D41, DIV I DRYWELL TEMPERATURE HIGH, alarms.

T47-R803A, Drywell Cooling System Area Temperatures, Div 1, point 24, Drywell Average Temperature indicates 147°F (stable).

3D81, PRIMARY CONTAINMENT PRESSURE HIGH / LOW, alarms.

T50-R802A, Div 1 PC Pressure Recorder indicates 1.60 psig (stable).

3D156, REACTOR WATER LEVEL LOW, alarms.

C32-R614, RPV Narrow Range Level indicates 190 inches (stable).

8D46, DIV 1 REACTOR BLDG PRESSURE HIGH / LOW, alarms.

T41-R800A, Div 1 CR and RB Diff Press Recorder indicates RB D/P indicates

-0.125 (minus 0.125) inches water column.

With these indications the CRS will FIRST direct entry into A. 29.100.01 Sheet 1, "RPV Control" ONLY.

B. 29.100.01 Sheet 2, "Primary Containment Control" ONLY.

C. 29.100.01 Sheet 5, "Secondary Containment Control and Rad Release" ONLY.

D. 29.100.01 Sheet 1, "RPV Control" AND 29.100.01 Sheet 2, "Primary Containment Control."

Answer: B Answer Explanation:

The only EOP entry condition is high drywell temperature.

ILO EXAM Page: 15 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 6 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26745 User-Defined ID: S06 Cross Reference 802-3004-000-0004-006 Number:

Topic: Select appropriate EOP based on plant conditions.

Num Field 1: LOK L Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because you have not exceeded 1.68psig.

C. is incorrect because RB d/p is negative.

D. is incorrect because you have not exceeded 1.68psig.

Reference:

29.100.01 SH 2, entry conditions Question 6 Table-Item Links Plant Procedures 29.100.01 SH 2 NUREG 1123 KA Catalog Rev. 2 295028 EA2.01 4.0*/4.1* Drywell temperature Associated objective(s):

Select the appropriate EOP / AOP based on plant conditions.

ILO EXAM Page: 16 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 7 ID: S07 Points: 1.00 The plant is operating at 100%, when a confirmed fire develops in the HPCI Quad. Ten minutes later, Fire Brigade Leader reports the fire is out and requests to isolate the sprinklers in the HPCI room. ARP 2D105 REAC BLDG CORNER ROOMS/HPCI ROOM FLOOD LEVEL is alarming. After isolating the sprinklers, Fire Brigade Leader reports that there is NO apparent damage to any HPCI components due to the fire, but there is about 2 feet of water on the floor.

What is the operability status of HPCI and reason for this status?

A. OPERABLE, as long as the sprinkler system is declared inoperable and an hourly fire watch is stationed.

B. OPERABLE, as long as the sprinkler system is declared inoperable and a continuous fire watch is stationed.

C. NOT OPERABLE due to the sprinkler system being inoperable with the isolation valve closed.

D. NOT OPERABLE due to flooding in the HPCI room.

Answer: D Answer Explanation:

2D105 states IF flooding is apparent in the HPCI Room, declare HPCI inoperable.

ILO EXAM Page: 17 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.50 System ID: 26747 User-Defined ID: S07 Cross Reference NEW Number:

Topic: Operability of HPCI during HPCI Room Flooding.

Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 2 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because this would be true if there were no flooding and the HPCI pump was in a different Zone per TR 3.12.3.

B. is incorrect because this would be true if there were no flooding per TR 3.12.3.

C. is incorrect because this would be true if you could not meet Condition A of TR3.12.3 and there was no flooding.

Reference:

2D105 Question 7 Table-Item Links Plant Procedures 02D105 NUREG 1123 KA Catalog Rev. 2 600000 AA2.14 3/3.6 Equipment that will be affected by fire suppression activities in each zone G2.2.37 3.6/4.6 Ability to determine operability and/or availability of safety related equipment ILO EXAM Page: 18 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Given plant conditions that constitute non-compliance with any LCO, apply Technical Specifications and Bases to determine the applicable Condition(s),

Required Action(s), and associated Completion Time(s).

ILO EXAM Page: 19 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 8 ID: S08 Points: 1.00 The plant is operating at 60% power. Digital Feedwater Level Control is in 3-Element control with the Reactor Level Select Switch in A. 3D164, FEEDWATER CONTROL DCS TROUBLE has alarmed, and both Reactor Feedwater Pump Controllers have switched to Emergency Bypass. RPV Level is 196 inches and slowly lowering.

What action is required by procedure?

A. Perform SOP 23.107. PLACE the Level Control Mode Switch in 1 ELEM, and continue power operation in Single Element Control.

B. Perform SOP 23.107. PLACE both Emergency Bypass switches in position "M", manually adjust Reactor Feedwater Pump Controllers to match Feed Pump speeds, and continue power operation in 3 Element Control.

C. Enter AOP 20.107.01. North and South Reactor Feedwater Pump speeds will lower. Adequate Pumping capacity is NOT available. The Reactor Mode Switch must be placed in Shutdown.

D. Enter AOP 20.107.01. PLACE both Emergency Bypass switches in position "M", manually adjust Reactor Feedwater Pump Controllers to match Feed Flow with Steam Flow, and continue power operation with manual feed pump speed control.

Answer: D Answer Explanation:

With both Reactor Feed Pump Controllers in EMERGENCY BYPASS, manual feedwater control is required by the AOP to maintain level.

ILO EXAM Page: 20 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26778 User-Defined ID: S08 Cross Reference 2011 LOR EXAM #2 Number:

Topic: Direct actions for Loss of Feedwater Control Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A is plausible; would be true for a loss of one feed flow or two steam flow inputs, if NOT in Emergency Bypass.

B is a plausible misconception in that matching RFP speeds would be effective vice matching steam flow and feed flow.

C is plausible misconception; testing knowledge of pumping capacity with controllers in Emergency Bypass.

References:

20.107.01, page 9; 23.107, page 8 Question 8 Table-Item Links Plant Procedures 20.107.01 23.107 NUREG 1123 KA Catalog Rev. 2 295009 AA2.02 3.6/3.7 Steam flow/feed flow mismatch ILO EXAM Page: 21 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Direct and Monitor the shift team during performance of an emergency / abnormal operating procedures.

ILO EXAM Page: 22 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 9 ID: S09 Points: 1.00 During a reactor startup control rods are being withdrawn and reactor pressure is being raised to 944 psig when the running CRD pump trips due to low suction pressure. The plant conditions are as follows:

RPV water level .................................. 190 inches

RPV pressure ...................... 850 psig slowly rising

3D10, CRD ACCUMULATOR TROUBLE, actuates on a Control Rod at full in position.

Given these plant conditions, which of the following is first directed by plant procedures?

A. Place CRD Flow Controller in MANUAL, and close CRD Flow Control Valve.

B. Within 20 minutes, place the Reactor Mode switch in SHUTDOWN.

C. Immediately place the Reactor Mode switch in SHUTDOWN.

D. Start the Standby CRD Pump.

Answer: A Answer Explanation:

This is the first action required, overrides do not apply.

ILO EXAM Page: 23 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 26819 User-Defined ID: S09 Cross Reference 315-0109-000-0006-007 Number:

Topic: Actions for Loss of CRD Hydraulics Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 2 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because this is an override action if Reactor Pressure >900 psig, more than one accumulator trouble light received(at least one on a withdrawn control rod), and no CRD Pump running.

C. is incorrect because this is an override action with Reactor pressure less than 900 psig, and a CRD accumulator trouble on a withdrawn control rod.

D. is incorrect because this action is done after placing CRD Flow Controller in MANUAL and close CRD Flow Control Valve

Reference:

20.106.01, page 3 Question 9 Table-Item Links Plant Procedures 03D010 20.106.01 NUREG 1123 KA Catalog Rev. 2 295022 AA2.02 3.3/3.4 CRD system status ILO EXAM Page: 24 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Direct and Monitor the shift team during performance of an emergency / abnormal operating procedures.

ILO EXAM Page: 25 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 10 ID: S10 Points: 1.00 The plant is operating at 85% power.

At 1355, a seismic event occurs.

At 1400, 1D66 Steam Leak Detection Ambient Temp High alarms. Steam tunnel temperature is 170°F and rising 5°F/Min. RWCU indicates isolated. RWCU Hx room temperature is 175°F and increasing 2°F/min.

As CRS, what action shall you direct FIRST, and reason for this action?

A. After a brief, place the Reactor Mode switch in SHUTDOWN. This will reduce the energy being discharged into secondary containment and prevent automatic scram on MSIV closure.

B. Immediately shut MSIVs. This will prevent a primary system from discharging into secondary containment.

C. At 1408, place the Reactor Mode Switch in SHUTDOWN. Required action due to exceeding max safe temperature, protecting plant equipment.

D. At 1420, open 5 SRVs (ADS preferred). This will reduce the energy being discharged into secondary containment (two area temperatures greater than max safe).

Answer: A Answer Explanation:

Indications give two area temperatures greater then max normal, which requires isolation of any primary system discharging into secondary. MSIVs shutting automatically scram the reactor. The mode switch is taken to shutdown prior to shutting the MSIVs.

ILO EXAM Page: 26 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 26820 User-Defined ID: S10 Cross Reference NEW Number:

Topic: Actions on Steam Leak Detection alarms.

Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

B. is plausible; this is a valid action, but would cause an automatic scram, so the mode switch is taken to shutdown prior to this action.

C. is plausible; based on the leak rate, steam tunnel temperate would be 210°F. This is the max safe temperature. EOPs direct you to place mode switch in shutdown prior to reaching this temperature. You would also get a MSIV isolation at this time.

D. is plausible; at 1408, the reactor would scram on MSIV closure. At 1420, you would get your second area temperature >max safe, requiring an ED.

Reference:

29.100.01 SH 5, SC-3 ILO EXAM Page: 27 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 10 Table-Item Links Plant Procedures 29.100.01 SH 5 NUREG 1123 KA Catalog Rev. 2 295032 EK3.02 3.6/3.8 Reactor SCRAM G2.4.21 4.0/4.6 Knowledge of the parameters and logic used to assess the status of safety functions such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Associated objective(s):

Direct and Monitor the shift team during performance of an emergency / abnormal operating procedures.

ILO EXAM Page: 28 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 11 ID: S11 Points: 1.00 The plant is operating in Mode 2 when the following alarms occur:

1D6, DIV 1 CSS LOGIC POWER FAILURE

1D13, TESTABILITY DIV 1 ECCS LOGIC/POWER FAILURE Which one of the following describes the impact of this indication on the Core Spray System and what action is required?

A. Automatic operation of Div 1 CSS will be inhibited but manual injection remains functional. Core Spray Loop A is NOT required because Core Spray Loop B satisfies the Technical Specification LCO 3.5.1 indefinitely in the present mode.

B. Automatic and manual operation of Div 1 CSS will be inhibited. Core Spray is required to be OPERABLE in the present MODE. Div 1 CSS must be restored within 7 days.

C. Automatic and manual operation of Div 1 CSS remain functional. Core Spray Loop A is assured to produce the required flow and satisfies the Technical Specification LCO 3.5.1 indefinitely.

D. Automatic and manual operation of Div 1 CSS remain functional but E2150-F031A, DIV 1 CS Pumps MM Flow Valve, Auto closes. Core Spray Loop A is NOT assured to produce the required flow. Div 1 CSS must be restored in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Answer: B Answer Explanation:

The alarms indicate that the DC power to CSS Logic A has had a failure. This will prevent Automatic and Manual injection of Div 1 CSS. The pumps can be manually started but the injection valves are incapable of opening. Both divisions of CSS are required to be operable in Mode 2 and a 7 day LCO must be entered.

ILO EXAM Page: 29 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 26878 User-Defined ID: Sll Cross Reference NEW Number:

Topic: Impact of Loss of DC Power to CS Logic A Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because the injection valves FOO4A and FOO5A are interlocked closed and require a signal from CSS Logic A to open.

C. is incorrect because DC Logic power has been lost and both Auto and Manual injection will be inhibited.

D. is incorrect because DC Logic power has been lost and both Auto and Manual injection will be inhibited.

Reference:

Tech Spec 3.5.1 Question 11 Table-Item Links Plant Procedures 01D06 NUREG 1123 KA Catalog Rev. 2 209001 A2.04 2.9/3 D.C. failures Technical Specifications 3.5.1 ECCS Operating ILO EXAM Page: 30 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Discuss failure modes of Core Spray System controls and vital instruments, including design features that could result in erroneous operation or indication.

ILO EXAM Page: 31 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 12 ID: S12 Points: 1.00 A reactor startup is in progress with Intermediate Range Monitor (IRM) Channel A INOPERABLE and BYPASSED, when the following occurs:

IRM Channel D indicates upscale at 125/125, irrespective of Range Switch position.

IRM Channels B, C, E, F, G, and H indicate 32/40 on Range 7.

ALL Average Power Range Monitors (APRMs) are DOWNSCALE.

Which one of the following actions shall be directed?

A. PLACE IRM Channel D in a TRIPPED condition, and continue the Reactor Startup.

B. SHUTDOWN per GOP 22.000.04, Plant Shutdown from 25% power because REQUIRED Intermediate Range Monitors are INOPERABLE.

C. BYPASS the IRM Channel D using the bypass joystick per 23.603, Intermediate Range Monitors. RESET the Half Scram, and CONTINUE the Reactor Startup.

D. BYPASS IRM Channel D by placing the Reactor Mode Switch in RUN per GOP 22.000.02, Plant Startup from 25% power. RESET the Half Scram, and CONTINUE the Reactor Startup.

Answer: C Answer Explanation:

3 IRMs per RPS Trip System are OPERABLE. Directed actions include BYPASSING the IRM Channel D ROD BLOCK using the joystick per 23.603; RESETTING the Half SCRAM, and continuing the Reactor Startup.

ILO EXAM Page: 32 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26879 User-Defined ID: S12 Cross Reference 315-0023-000-0013-001 Number:

Topic: IRM Tech Spec Operability during Startup Num Field 1: LOK H Num Field 2: 10 CFR 55.43 (b) 2 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because IRM is in a TRIPPED condition, needs to be BPASSED to continue startup.

B. is incorrect would be true with an additional IRM in either TRIP system INOPERABLE.

D. is incorrect because Reactor Power is too low to place Mode Switch in RUN.

Reference:

23.603, page 3 Question 12 Table-Item Links Plant Procedures 23.603 03D060 NUREG 1123 KA Catalog Rev. 2 215003 A2.04 3.7/3.8 Up scale or down scale trips Technical Specifications 3.3.1.1 Reactor Protection System (RPS) Instrumentation ILO EXAM Page: 33 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Identify Intermediate Range Monitoring System related technical specifications, with emphasis on action statements requiring prompt actions (for example, one hour or less).

ILO EXAM Page: 34 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 13 ID: S13 Points: 1.00 The plant is being shutdown using 22.000.04 PLANT SHUTDOWN FROM 25%

POWER. Step 6.2.12 states "Record time the SRM channel functional test is due." When is this surveillance required to be done during a GOP shutdown?

SRM Channel Functional Test must be performed within _(1)_ of IRMs on Range

_(2)_ or below.

A. (1) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (2) 4 B. (1) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (2) 2 C. (1) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (2) 2 D. (1) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (2) 4 Answer: C Answer Explanation:

SRM Channel Functional Test must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of IRMs on Range 2 or below.

ILO EXAM Page: 35 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26880 User-Defined ID: S13 Cross Reference NEW Number:

Topic: SRM Channel Functional Test requirements Num Field 1: LOK L Num Field 2: 10 CFR 55.43(b) 2 Text Field: 2012 ILO Exam Comments: Justification:

A/B/D. SRM Channel Functional Test must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of IRMs on Range 2 or below. The other listed times (1, 8, 24) is a possible operator misunderstanding. The IRM ranges can also be confused with other IRM range requirements.

Reference:

22.000.04, page 30 Question 13 Table-Item Links Plant Procedures 22.000.04 NUREG 1123 KA Catalog Rev. 2 215004 A4.07 3.4/3.6 Verification of proper functioning/ operability G2.1.20 4.6/4.6 Ability to execute procedure steps Technical Specifications 3.3.1.2 Source Range Monitor (SRM) Instrumentation ILO EXAM Page: 36 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Describe the Source Range Monitoring System technical specification limiting conditions for operation, their bases, the associated surveillance requirement(s),

and their relationship to operability.

ILO EXAM Page: 37 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 14 ID: S14 Points: 1.00 The plant is stable at 75% power, control rods are being withdrawn. Control rod 22-23 is selected for withdraw. If APRM Channel 2, RECIRCULATION FLOW PROCESSING UNIT fails downscale, what protective functions automatically occur (1) ? What procedure-driven actions, if any, would allow continued operations (2) ?

A. (1) No protective functions occur.

(2) Continued rod withdraw in accordance with 23.623, "Reactor Manual Control System."

B. (1) Only a Control Rod Block due to APRM 2 Simulated Thermal Power Upscale.

(2) Bypass the affected RBM in accordance with 23.607, "Rod Block Monitoring System."

C. (1) Half SCRAM and Control Rod Block due to APRM 2 Simulated Thermal Power Upscale and Trip.

(2) Reset the Half SCRAM and bypass the affected APRM in accordance with 23.605 "Average Power Range Monitoring System."

D. (1) RBM Trouble Alarm and Control Rod Block due to APRM 2 Simulated Thermal Power Upscale and Trip.

(2) Bypass the affected APRM in accordance with 23.605 "Average Power Range Monitoring System."

Answer: D Answer Explanation:

Recirculation flow processing unit failing low would result in APRM STP upscale trip setpoint being less than the current power level (61.4% < 75%). This would result in a RBM trouble alarm, Control Rod block and APRM STP upscale trip. TS allows operation with 3 APRMs and bypassing APRM 2 would allow continued operation.

ILO EXAM Page: 38 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 26881 User-Defined ID: S14 Cross Reference 315-0124-000-0001-007 Number:

Topic: APRM Recirc Flow Unit failure Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because a APRM STP upscale trip would occur as a result of the flow processing unit failing low.

B. is incorrect because in addition to a control rod block, a RBM Trouble alarm would occur as a result of flow deviation between any two flow signals.

C. is incorrect because 2 or more APRMs indicating an upscale trip would cause a Reactor Scram and not a Half Scram.

Reference:

23.605 Enclosure A Question 14 Table-Item Links Plant Procedures 23.605 03D101 NUREG 1123 KA Catalog Rev. 2 215005 A2.05 3.5/3.6 Loss of recirculation flow signal ILO EXAM Page: 39 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Discuss failure modes of Power Range Neutron Monitoring System controls and vital instruments, including design features that could result in erroneous operation or indication.

ILO EXAM Page: 40 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 15 ID: S15 Points: 1.00 The plant was operating at 100% power when an earthquake occurs resulting in a Station Blackout and reactor recirculation loop leak. (1) What action shall be prioritized and (2) the bases for this action?

A. (1) Place HPCI Logic A/B keylock switches in TEST.

(2) To prevent HPCI isolation as a result of high room temperature.

B. (1) Confirm initiation of EECW.

(2) To ensure adequate cooling of safety related equipment.

C. (1) Open 13.2 kV Pos A6.

(2) Allows for SST 64 alternate power to energize SST 64.

D. (1) Verify CTG 11-1 Blackstart Unit Auto starts.

(2) CTG11 Unit 1 operation will allow energizing SST 64, SST 66 and SST 68.

Answer: A Answer Explanation:

Both the HPCI and RCIC rooms have equipment area high temperature sensors, which are capable of causing isolation of the HPCI or RCIC systems.

ILO EXAM Page: 41 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26976 User-Defined ID: S15 Cross Reference NEW Number:

Topic: SBO HPCI hi temp override Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because EECW has no power and is incapable of fulfilling its purpose.

C. is incorrect because CTG-11-1 would have to be started and position A6 would have to be closed.

D. is incorrect because CTG-11-1 is not capable of auto starting.

Reference:

20.300.SBO, page 3 Question 15 Table-Item Links Plant Procedures 20.300. SBO NUREG 1123 KA Catalog Rev. 2 G2.4.22 3.6/4.4 Knowledge of the bases for prioritizing safety functions during emergency operations 262001 A2.03 3.9/4.3 Loss of off-site power Associated objective(s):

Given a copy of electrical AOPs, analyze and determine which equipment has the highest priority for restoration.

ILO EXAM Page: 42 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 16 ID: S16 Points: 1.00 The operating crew is currently performing a Rod Pattern Adjustment from Group 10 to Group 9 Control Rods. While withdrawing a Control Rod, alarm 3D80, Control Rod Drift, is received for a single Control Rod.

What impact does this have on the Reactor Manual Control System, and what actions shall be ordered?

A. A rod block is enforced. The Control Rod should be disarmed at its current position.

B. The ability to move control rods remains functional. The Control Rod should be fully inserted and disarmed.

C. Only the RONOR switch can be used to move control rods. The Control Rod should be individually scrammed.

D. Only the "Emergency In" position of the RONOR switch is functional.

Place the Reactor Mode switch in SHUTDOWN.

Answer: B Answer Explanation:

Only a Control Rod Drift occurred. The RMCS remains functional, and the Control Rod should be fully inserted and disarmed.

ILO EXAM Page: 43 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26882 User-Defined ID: S16 Cross Reference NEW Number:

Topic: Actions for Control Rod Drift Num Field 1: LOK L Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because a Rod Block alarm is not received.

C. is incorrect because although the RONOR switch is functional the RMCS is also functional, the rod is not scrammed unless it drifts after it has been disarmed.

D. is incorrect because the RMCS is functional and the mode switch is only placed in SHUTDOWN if 2 or more rods are drifting.

Reference:

20.106.07, pages 5 & 6 Question 16 Table-Item Links Plant Procedures 20.106.07 NUREG 1123 KA Catalog Rev. 2 201002 A2.02 3.2/3.3 Rod drift alarm Associated objective(s):

Direct and Monitor the shift team during performance of an emergency / abnormal operating procedures.

ILO EXAM Page: 44 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 17 ID: S17 Points: 1.00 Following an Emergency Depressurization under ATWS conditions the following conditions exist:

RPV Water Level indications are UPSCALE due to High Drywell and Reactor Building Temperatures.

Injection has been Terminated and Prevented.

3 Safety Relief Valves are OPEN.

Reactor Pressure is 300 psig.

Reactor Power is 20%.

Under these conditions, which one of the following describes the status of Core Cooling?

MINIMUM Table STEAM COOLING 8 PRESSURE (MSCP)

No of MSCP open SRVs (PSIG) 5 or more 230 4 290 3 392 2 595 Adequate Core Cooling is:

A. ASSURED by core submergence.

B. ASSURED by sufficient steam flow through OPEN Safety Relief Valves.

C. NOT ASSURED because injection is insufficient to cool the core.

D. NOT ASSURED because an inadequate number of Safety Relief Valves are OPEN.

Answer:

Answer Explanation:

Justification- with Reactor pressure above 290 psig and 4 SRVs have to be open to assure ACC by sufficient steam flow through the SRVs.

ILO EXAM Page: 45 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 26961 User-Defined ID: S17 Cross Reference 802-3003-000-0004-008(M)

Number:

Topic: ACC with given conditions Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is plausible; it would be true if level was valid upscale.

B. is incorrect, but would be true if there were 5 SRVs open.

C. is incorrect, with injection being terminated and prevented and no level indication, ACC is not assured through submergence.

Reference:

29.100.01 SH 3A, Table 21 Question 17 Table-Item Links Plant Procedures 29.100.01 SH 3A NUREG 1123 KA Catalog Rev. 2 216000 K3.24 3.9/4.1 Vessel level monitoring G2.2.44 4.2/4.4 Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions ILO EXAM Page: 46 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Describe the two methods of assuring adequate core cooling.

ILO EXAM Page: 47 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 18 ID: S18 Points: 1.00 Following a reactor scram due to a turbine trip, the following conditions exist:

Reactor Power is 2% and slowly lowering.

Torus Temperature is 115°F and rising.

Drywell Pressure is 1.4 psig and steady.

SLC is injecting.

Division 2 RHR is in Torus Cooling and Torus Spray.

RPV water level is currently 63 inches with a level band of 50 to 100 inches.

The CRNSO reports he is out of his water level band LOW.

1D29 RHR INIT REAC VESSEL H2O LEVEL Ll alarms (1) What is the specific effect on DIV 2 RHR, and (2) what actions would you direct to recover DIV 2 RHR to Torus Cooling and Spray?

A. (1) E1150-F028B, Div 2 RHR Torus Iso Vlv. closes.

(2) DIV 2 RHR must be filled and vented before restoring per SOP 20.205.

B. (1) E1150-F027B, Div 2 RHR Torus Spray Iso and E1150-F024B, Div 2 RHR Torus Clg Iso, close.

(2) Containment Spray Mode Select Switch must be placed in MANUAL, and F027B and F024B opened.

C. (1) E1150-F027B, Div 2 RHR Torus Spray Iso and E1150-F024B, Div 2 RHR Torus Clg Iso, close.

(2) Containment Spray 2/3 Core Height Override Switch must be placed in MANUAL OVERRIDE, and F027B and F024B opened.

D. (1) E1150-F027B, Div 2 RHR Torus Spray Iso and E1150-F024B, Div 2 RHR Torus Clg Iso, close. .

(2) Containment Spray 2/3 Core Height Override Switch must be placed in MANUAL OVERRIDE, Containment Spray Mode Select Switch must be placed in MANUAL, and F027B and F024B opened.

Answer: B ILO EXAM Page: 48 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Answer Explanation:

Justification- Due to level going below level 1, E1150-F027 B, Div 2 RHR Torus Spray Iso and E1150-F024 B, Div 2 RHR Torus Clg Iso, close. This would be prevented if Containment Spray Mode Select Switch was placed in MANUAL.

This is not done unless there is a DW Presure >1.68 or Ll which is not present in the initial conditions. To restore, these valves must be re-opened after Containment Spray Mode Select Switch is placed in MANUAL.

Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 26981 User-Defined ID: S18 Cross Reference NEW Number:

Topic: Torus cooiling/sprays affect with Ll Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 10 Text Field: 2012 ILO Exam Comments: Plausible Distractors:

A. is plausible; Justification:

A. is plausible; E1150-F028 B, Div 2 RHR Torus Iso Vlv has a key lock to open, but does not shut automatically (student misconception).

C. is plausible you do not place Containment Spray 2/3 Core Height Override Switch in MANUAL OVERRIDE until RPV level is below Level 0.

D. is plausible you do not place Containment Spray 2/3 Core Height Override Switch in MANUAL OVERRIDE until RPV level isbelow Level 0.

Reference:

23.205, Enclosure A ILO EXAM Page: 49 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 18 Table-Item Links Plant Procedures 23.205 NUREG 1123 KA Catalog Rev. 2 230000 A2.03 2.9/3.2 Valve closures Associated objective(s):

List the automatic features of RHR System operations.

ILO EXAM Page: 50 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 19 ID: S19 Points: 1.00 The plant is operating at 100%. The SM is reviewing the POD for the upcoming week.

Which one of the following evolutions would require coverage from a Reactivity Management SRO (RMSRO)?

A. HPCI surveillance B. Turbine Valve Testing surveillance C. Power change required for CRD Operability D. Down power to support removal of Reactor Feed Pump from service Answer: D Answer Explanation:

Per MOP-19, Reactivity changes requiring a Reactivity Management Senior Reactor Operator (RMSRO) are planned changes to Control Rod position or Recirculation pump speed including load drops of greater than 30% and restoration with major BOP equipment manipulations.

ILO EXAM Page: 51 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 27058 User-Defined ID: S19 Cross Reference NEW Number:

Topic: Requirement For Reactivity Management Coverage Num Field 1: LOK L Num Field 2: 10 CFR 55.43b) 3 Text Field: 2012 ILO Exam Comments: Justification:

A/B/C Is incorrect because these are identified in ODE-1 as examples of minor reactivity manipulations not requiring a RMSRO.

Reference:

MOP19, pages 3 & 5 Question 19 Table-Item Links Plant Procedures ODE-01 Reactivity Management MOP19 NUREG 1123 KA Catalog Rev. 2 G2.1.15 2.7/3.4 Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, operations memos, etc.

Associated objective(s):

Define the Roles and Responsibilities established at Fermi 2 regarding Reactivity Management.

ILO EXAM Page: 52 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 20 ID: S20 Points: 1.00 During core alterations with fuel movements, in addition to minimum shift complements per MOP 3 Policies and Practices, what is the minimum shift complement required per MOP 13?

1 Refuel Floor Supervisor, 1 Fuel Handler, A. and no others required B. and 1 Fuel Movement Verifier C. 1 Fuel Movement Verifier, and 1 Reactor Engineer D. 1 Fuel Movement Verifier, 1 Reactor Engineer, and 1 Refuel Floor Coordinator Answer: B Answer Explanation:

The minimum shift complement for core alterations shall consist of those positions listed in MOP03, "Policies and Practices," plus one Refuel Floor Supervisor, and During fuel movements, additional positions requirement of one (1) fuel handler, and one (1) Fuel Movement Verifier.

ILO EXAM Page: 53 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 27039 User-Defined ID: S20 Cross Reference NEW Number:

Topic: Fuel Movement Shift Compliment Num Field 1: LOK L Num Field 2: 10 CFR 55.43(b) 7 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because there is no Fuel Movement Verifier C. is incorrect because Reactor Engineer is not required D. is incorrect because Reactor Engineer and Refuel Floor Coordinator are not required

Reference:

MOP13, page 2 Question 20 Table-Item Links Plant Procedures MOP13 NUREG 1123 KA Catalog Rev. 2 G2.1.42 2.5/3.4 Knowledge of new and spent fuel movement procedures ILO EXAM Page: 54 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Describe methods used to control Operation's activities during refueling outages, including:

a. Refuel Floor Supervisor's responsibilities during refueling outages.

b. Minimum Refuel Floor complement during core alterations.

c. Access control for the Refuel Floor when core alterations are in progress.

d. Methods for controlling refuel floor activities during non-refuel outage conditions.

ILO EXAM Page: 55 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 21 ID: S21 Points: 1.00 With the plant operating at 95% power, the B21-N091A Wide Range Reactor Water Level Instrument Transmitter FAILED LOW.

Which one of the following Technical Specification required instrument functions is NOT affected?

A. RPV Water Level Low L3, Reactor Scram.

B. RPV Water Level Low L2, ATWS Initiation.

C. RPV Water Level High L8, RCIC Turbine Trip.

D. RPV Water Level Low Ll, Core Spray / LPCI / EDG Start.

Answer: A Answer Explanation:

The B21-N091A Wide Range Reactor Water Level Instrument Transmitter inputs to trip units B21-N91A(L10, N692A(L2), & N693A(L8). Only level function not affected is L3. See 23.601, pages 16-19.

ILO EXAM Page: 56 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.50 System ID: 27038 User-Defined ID: S21 Cross Reference 315-0121-000-A008-010 Number:

Topic: Tech Spec Level Instrument Failure Num Field 1: LOK L Num Field 2: 10 CFR 55.43(b) 2 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because B21-N692A inputs to ATWS L2 trip.

C. is incorrect because B21-N693 A& B are required for RCIC L8 trip.

D. is incorrect because B21-N693A inputs to Ll, Core Spray/LPCl/EDG Start.

Reference:

23.601, pages 16-19 Question 21 Table-Item Links Plant Procedures 23.601 NUREG 1123 KA Catalog Rev. 2 G2.2.40 3.4/4.7 Ability to apply technical specifications for a system Associated objective(s):

At the completion of this training, the licensed operator candidate will recognize conditions, apply the rules and terminology, and properly implement actions for conditions of plant equipment that are impacted by the Fermi 2 Technical Specifications.

ILO EXAM Page: 57 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 22 ID: S22 Points: 1.00 A discharge permit has been submitted to the Shift Manager for approval. The permit indicates, the water to be discharged is potentially contaminated and will be discharged from an area subject to radiological restrictions. The actions required by MRP18, Release of Potentially Clean Fluids, have been completed.

Upon deciding to approve the discharge permit, the Shift Manager shall assign an expiration not to exceed:

A. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. end of scheduled shift C. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. 5 days Answer: C Answer Explanation:

Per MCE 06 NON-RADIOLOGICAL ENVIRONMENTAL PROTECTION, Pumping of sources within an area subject to radiological restrictions should be assigned an expiration not to exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from the time the permit is approved.

ILO EXAM Page: 58 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 27019 User-Defined ID: S22 Cross Reference 802-4101-000-0003-007 Number:

Topic: Discharge Permit Expiration Time Num Field 1: LOK L Num Field 2: 10 CFR 55.43(b) 4 Text Field: 2012 ILO Exam Comments: Justification:

A/B/D. is incorrect because Pumping of sources within an area subject to radiological restrictions should be assigned an expiration not to exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from the time the permit is approved.

Reference:

MCE06, page 15 Question 22 Table-Item Links Plant Procedures MCE06 NUREG 1123 KA Catalog Rev. 2 G2.3.6 2.0/3.8 Ability to approve release permits ILO EXAM Page: 59 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Describe the methods used at Fermi 2 to protect the environment, including:

a. Conditions that would indicate an NPDES Non-Compliance, and actions required in the event of a non-compliance.

b. The different Environmental Protection Plan documents used at Fermi 2.

c. Notifications required for Unusual or Important Environment Events.

d. Actions that must be taken when a Non-Radiological Environmental Spill occurs.

e. Actions taken when finding unidentified/unattended waste.

ILO EXAM Page: 60 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 23 ID: S23 Points: 1.00 A loss of drywell cooling occurs followed by a large LOCA. Several hours after the LOCA the following conditions exist:

Reactor power .................................. <3% (all rods full in)

RPV pressure ........................................... 50 psig (stable)

Drywell temperature .................................. 250°F (stable)

Drywell pressure ....................................... 42 psig(rising)

Torus pressure .......................................... 45 psig (rising)

Primary containment water level ................... 565 feet elev As CRS, what action shall you direct, and reason for this action?

A. Initiate Drywell Sprays to maintain primary containment integrity.

B. Vent the torus, only if release rates remain below radioactivity release limits to minimize dose to public.

C. Vent the drywell to maintain primary containment integrity.

D. Vent the torus to reduce radioactivity released by the scrubbing action of the Torus water.

Answer: D Answer Explanation:

Because you vent the torus if water level is less than 570 feet, the reason you choose the torus is because of the scrubbing action. This is done regardless of offsite release rates..

ILO EXAM Page: 61 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.50 System ID: 27018 User-Defined ID: S23 Cross Reference NEW Number:

Topic: Venting Torus Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A. is incorrect because torus water level is above

+45 inches thus questioning the operability of the vacuum breakers. Step PCP-7 of 29.100.01 SH 2.

B. is incorrect because you vent the torus regardless of the release rate.

C. is incorrect because the DW is vented if torus water level is greater than 570 feet or the torus cannot be kept below the PCPL.

Reference:

29.100.01 SH 2, PCP-15 Question 23 Table-Item Links Plant Procedures 29.100.01 SH 2 NUREG 1123 KA Catalog Rev. 2 G2.3.11 3.8/4.3 Ability to control radiation releases ILO EXAM Page: 62 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Associated objective(s):

Describe plant conditions that would require use of the alternative actions contained in 29.100.01 Sh 2 and Sh 4, Primary Containment Control, including:

a. Emergency Depressurization

b. Torus Spray

c. Drywell Spray

d. Venting the Drywell

e. Venting the Torus ILO EXAM Page: 63 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 24 ID: S24 Points: 1.00 An ALERT Emergency Action Level has been declared. Which facilities must be activated?

A. TSC only B. TSC and OSC only C. TSC, OSC, and EOF only D. TSC, OSC, EOF, and JIC Answer: C Answer Explanation:

Per EP-103, TSC, OSC, and EOF must be activated on step 4 of the Alert Checklist for Immediate Actions.

ILO EXAM Page: 64 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 2.00 System ID: 27080 User-Defined ID: S24 Cross Reference NEW Number:

Topic: Activate Facilities in ALERT Num Field 1: LOK L Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

A/B. is incorrect because the EOF must be activated for an ALERT per EP-103.

D. is incorrect because the JIC is not activated until a SAE.

Reference:

EP-103, page 3, section 4.3, and ALERT checklist Question 24 Table-Item Links Plant Procedures EP-103 NUREG 1123 KA Catalog Rev. 2 G2.4.38 2.4/4.4 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required Associated objective(s):

Given a plant condition requiring event classification, determine protective measures for on-site personnel in accordance with emergency plan procedures.

ILO EXAM Page: 65 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO 25 ID: S25 Points: 1.00 The plant is operating at 50% power and a transient has occurred. The following plant conditions exist 10 seconds later without any operator actions having been taken:

4D121, 345KV BKR POS CF OPEN alarms.

4D123, 345KV BKR POS CM OPEN alarms.

Generator Field Breaker 41CS is TRIPPED.

Main Turbine Bypass Valves indicate FULL OPEN.

1D61, SRV OPEN alarms.

Which one of the following actions is required FIRST?

A. ENTER 29.100.01 Sheet 1, RPV CONTROL and MANUALLY Scram the reactor.

B. ENTER 29.100.01 Sheet 1, RPV CONTROL, ENTER 29.100.01 Sheet 1A, ATWS RPV CONTROL, and INHIBIT ADS.

C. ENTER 29.100.01 Sheet 1, RPV CONTROL and MANUALLY OPEN additional Safety Relief Valves to lower pressure to 960 psig.

D. ENTER 29.100.01 Sheet 1, RPV CONTROL, ENTER 29.100.01 Sheet 1A, ATWS RPV CONTROL, and LOWER Recirculation MG Set Speeds to MINIMUM.

Answer: A Answer Explanation:

The turbine trip at the given power should result in a scram. When a scram signal is present and above 3%, sheet 1 entry is required. The first action is to insert a manual reactor scram.

ILO EXAM Page: 66 of 67 17 January 2012

EXAMINATION ANSWER KEY 2012 ILO Exam - SRO Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 3.00 System ID: 27098 User-Defined ID: S25 Cross Reference 802-3003-000-0003-015 Number:

Topic: When to Scram Reactor Num Field 1: LOK H Num Field 2: 10 CFR 55.43(b) 5 Text Field: 2012 ILO Exam Comments: Justification:

B. is incorrect because this action would be if a manual scram was unsuccessful.

C. is incorrect because this would be true if a normal scram condition with an SRV actuated.

D. is incorrect because this action would be if a manual scram was unsuccessful.

Reference:

29.100.01 SH 1, RC-1 Question 25 Table-Item Links Plant Procedures 29.100.01 SH 1 NUREG 1123 KA Catalog Rev. 2 G2.4.4 4.5/4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures Associated objective(s):

Given a set of plant conditions/actions taken and a current copy of 29.100.01 Sh 1 through 6, determine which step(s) is (are) to be directed by the CRS.

ILO EXAM Page: 67 of 67 17 January 2012

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