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Exam ILO NRC - RO update1
	ML13364A032
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Site:	Fermi
Issue date:	08/27/2013
From:	; Division of Nuclear Materials Safety III
To:	;
	Carl Moore
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ML11355A012	List: ML13364A032; ML13364A035;
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EXAMINATION ANSWER KEY 2013 ILO NRC - RO 1 ID: R01 Points: 1.00 The plant is operating at 100% power at end of core life. A power change was was completed 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago and conditions are as follows:

All rods out 80% Rated Core Flow Recirc Pump A speed is 75%

Recirc Pump B speed is 70%

Based on these conditions, what action is required? (See attached Power-to-Flow Map.)

A. Insert control rods to 95% power.

B. Lower Recirc Pump A speed to 70% to match pump speeds.

C. Maintain current parameters until Xenon has reached equilibrium.

D. Notify SNE of unexpected operation outside the Power to Flow Map.

Answer: D Answer Explanation Per MOP19, Reactor Engineering (SNE) shall be notified of all unplanned core reactivity changes and abnormalities.

Plausible Distractors:

A. Inserting control rods to lower power would place you back in the power to flow map but would require SNE permission.

B. Just making unsupervised core parameter changes is not allowed and could potentially lead to a more severe situation.

C. Again, if the operation is outside the normal power to flow map regions, the situation should be addressed immediately and corrected.

ILO EXAM Page: 1 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 3.00 System ID: 31866 User-Defined ID: R01 Cross Reference Number: 26639 Topic: Unplanned Core Reactivity Changes Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 4 Text Field: ILO 2013 mike Comments: K/A - Partial or Complete Loss of Forced Core Flow Circulation:

Ability to interpret reference materials, such as graphs, curves, tables, etc.

Copy of Power to Flow Map must be provided Question 1 Table-Item Links Plant Procedures 20.138.01 ODE-01 Reactivity Management MOP19 NUREG 1123 KA Catalog Rev. 2 G2.1.25 3.9/4.2 Ability to interpret station reference materials such as graphs, curves, tables, etc.

295001 Partial or Complete Loss of Forced Core Flow Circulation ILO EXAM Page: 2 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 2 ID: R02 Points: 1.00 The plant is operating at 100% when a bird strike results in a loss of 120KV. All systems operate as designed.

With no operator action, what is the MAXIMUM time the Division 1 ESF 260/130 VDC batteries are expected to maintain a cell voltage above 1.75 Vdc?

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Answer: C Answer Explanation With a loss of 120KV the battery chargers will have to be manually placed back in the charging state. The ESF batteries are designed to last at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months without the chargers in operation.

A is plausible, but incorrect time requirement of TS 3.8.4 and design calc B is plausible, but incorrect time requirement of TS 3.8.4 and design calc D is plausible, but incorrect time requirement of TS 3.8.4 and design calc Question 2 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: 31446 User-Defined ID: R02 Cross Reference Number: NEW Topic: DC operation Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 mike Comments: KA - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Effect of battery discharge rate on capacity ILO EXAM Page: 3 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 2 Table-Item Links

Do Not Use* - Operations Related Procedures 23.309 260/130v DC Electrical System (ESF & BOP)

NUREG 1123 KA Catalog Rev. 2 295003 AK1.01 2.7/2.9 Effect of battery discharge rate on capacity ILO EXAM Page: 4 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 3 ID: R03 Points: 1.00 The reactor has scrammed due to a LOSS of Offsite Power. ONLY EDGs 13 & 14 have started and loaded.

What is the current SOURCE of power for the station DC loads?

A. Division 1 Chargers are supplying Division 1 DC Loads. Division 2 Chargers are supplying Division 2 DC Loads.

B. Division 1 Batteries are supplying Division 1 DC Loads. Division 2 Chargers are supplying Division 2 DC Loads.

C. Division 1 Chargers are supplying Division 1 DC Loads. Division 2 Batteries are supplying Division 2 DC Loads.

D. Division 1 Batteries are supplying Division 1 DC Loads. Division 2 Batteries are supplying Division 2 DC Loads.

Answer: D Answer Explanation With ONLY EDGs 13 and 14 loaded, Div 1 and Div 2 DC loads are supplied by Batteries.

MANUAL action is required to reset Div 2 Chargers, which have power available.

A is plausible; is the normal configuration for DC Distribution.

B is plausible; would be selected if candidate had misconception that EDG 13 and 14 automatically reenergize Div 2 Chargers.

C is plausible; would be selected if candidate had misconception that EDG 13 and 14 automatically reenergize Div 1 Chargers.

Question 3 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: 31546 User-Defined ID: R03 Cross Reference Number: 315-0064-B000-001 Topic: LOOP - EDGs Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 Comments: KA - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following: Battery charger ILO EXAM Page: 5 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 3 Table-Item Links Plant Procedures 20.300.Offsite NUREG 1123 KA Catalog Rev. 2 295004 AK2.01 3.1/3.1 Battery charger ILO EXAM Page: 6 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 4 ID: R04 Points: 1.00 While operating at 100% power, the Generator Field Breaker 41CS on COP H11-P804 opens, causing a generator trip.

The generator trip occurred to protect against which ONE of the following conditions?

A. Excessive field voltage B. Main transformer overexcitation C. Excessive input current to the generator D. Damaging the Automatic Voltage Regulator (AVR)

Answer: C Answer Explanation Opening the field breaker would result in a loss of generator field and with the generator tied to the grid would result in high input current in the generator.

A is plausible, but opening the field breaker would prevent this.

B is plausible, but if volts per hertz exceed 114%, a turbine trip will result.

D is plausible, but fuse links and software control protect the AVR.

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: 31466 User-Defined ID: R04 Cross Reference Number: 315-0155-A010-001 Topic: MTG Trips Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP: Main generator trip ILO EXAM Page: 7 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 4 Table-Item Links Plant Procedures 23.118 NUREG 1123 KA Catalog Rev. 2 295005 AK3.04 3.2/3.2 Main generator trip ILO EXAM Page: 8 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 5 ID: R05 Points: 1.00 Reactor has scrammed and the plant has been stabilized. The CRS has directed the scram to be reset per 20.000.21, Reactor Scram. What action must be taken if a control rod does not settle to the 00 position following reset of the scram?

A. Verify rod position on the Rod Worth Minimizer B. Verify the Full In light is lit on the Full Core Display C. The control rod should be mechanically disarmed per 23.106 D. Attempt to withdraw or insert the control rod to 00 per 23.623 Answer: D Answer Explanation For control rods that did not settle to 00, the Reactor Scram AOP states to attempt to insert or withdraw CR to 00 per 23.623.

A. is plausible but the RWM would only display number of rods out and not position.

B. is plausible, but would not tell the position of the control rod.

C. is plausible, but would be performed if manual insertion or withdraw was unsuccessful.

Question 5 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: 35626 User-Defined ID: R05 Cross Reference Number: NEW Topic: Scram CR Position Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 6 Text Field: ILO 2013 Comments: KA - Ability to operate and/or monitor the following as they apply to SCRAM: Control Rod Position Question 5 Table-Item Links Plant Procedures 20.000.21 NUREG 1123 KA Catalog Rev. 2 295006 AA1.07 4.1/4.1 Control rod position ILO EXAM Page: 9 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 6 ID: R06 Points: 1.00 The plant is operating at 68% power when the Control Room is evacuated due to toxic fumes. A reactor scram could not be completed prior to evacuation.

Which of the following is the PREFERRED method of scramming the reactor and determining actions were successful?

A. Open Generator output breaker CF/CM, and verify APRMs indicate decreasing Reactor Power.

B. Open CB2A (C71-P001A) and CB2B (C71-P001B) and verify RPS Testability cabinet de-energized.

C. Turn off circuits 5 & 6 on Dist Cab 2PA-2 and 2PB-2, and verify RPS white Group Scram lights indicate off.

D. Take 2 operable APRM Mode switches out of operate, and verify APRMs indicate decreasing Reactor Power.

Answer: D Answer Explanation The Remote Shutdown Panel does not include reactor shutdown and turbine trip controls because it is assumed that reactor shutdown and turbine trip will be performed prior to leaving the Control Room. If this action is not possible, then reactor shutdown will be initiated by taking two APRMs out of operation per 20.000.19 SD from Outside the Control Room.

A is plausible; opening the breakers is an action from 20.000.18 ,Dedicated SD, and would result in a reverse power turbine trip and thus a reactor scram but is not the preferred method.

B is plausible, but not the preferred method.

C is plausible; action is required to remove power to SRVs to prevent a uncontrolled RPV blowdown for control of the plant from the dedicated shutdown panel based on fire in 3L zone.

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: 4.00 System ID: 31467 User-Defined ID: R06 Cross Reference Number: NEW Topic: CR Evacuation Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mike Comments: KA - Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT: Reactor power ILO EXAM Page: 10 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 6 Table-Item Links Plant Procedures 20.000.19 NUREG 1123 KA Catalog Rev. 2 295016 AA2.01 4.1*/4.1* Reactor power ILO EXAM Page: 11 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 7 ID: R07 Points: 1.00 The plant is operating at 100% with North and Center TBCCW Pumps in service, when the following occurs:

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

P43-R805, TBCCW Headers Pressure Indicator, indicates a d/p of 19 psi.

With these conditions, which one of the following is the correct diagnosis and required operator action?

A. TBCCW Differential Pressure is too LOW; START South TBCCW Pump.

B. TBCCW Differential Pressure is too HIGH; STOP an operating TBCCW Pump.

C. TBCCW Differential Pressure is too LOW; throttle closed P4300-F031, TBCCW Control Vlv Bypass Vlv.

D. TBCCW Differential Pressure is too HIGH; OPEN P43-F405, TBCCW DP Control Valve.

Answer: A Answer Explanation With Pressure Indicator below 20 psig, TBCCW Differential Pressure is too LOW. With degraded Pressure, starting the standby TBCCW Pump is directed by AOP 20.128.01, Loss of TBCCW System. Question requires person to determine if DP is HIGH or LOW based on a reported pressure indication, and select the appropriate mitigation response.

b. Is plausible, and would be appropriate per ARP 5D5 for Differential Pressure above 30 psig.

c. Is plausible, and is the required action for a complete loss of TBCCW or with indications of rising temperatures on the Main Turbine Generator Stator Water Cooling System.

d. Is plausible, and would be appropriate per ARP 5D5 for Differential Pressure above 30 psig if accompanied by 5D2, TBCCW PUMPS RECIRC VALVE CLOSED 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: 2.00 System ID: 31528 User-Defined ID: R07 Cross Reference Number: NEW Topic: TBCCW Pump trip Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 4 Text Field: ILO 2013 mike Comments: KA - Partial or Complete Loss of Component Cooling Water:

Knowledge of the purpose and function of major system components and controls.

ILO EXAM Page: 12 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 7 Table-Item Links Plant Procedures 20.128.01 05D005 NUREG 1123 KA Catalog Rev. 2 G2.1.28 4.1/4.1 Knowledge of the purpose and function of major system components and controls 295018 Partial or Complete Loss of Component Cooling Water ILO EXAM Page: 13 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 8 ID: R08 Points: 1.00 The IAS header has ruptured, and IAS pressure is approaching 20 psig. The reactor was manually scrammed, and RPV level dropped to 105 inches. RPV level was restored, and RPV level and pressure are now stabilized.

Currently, ventilation to the fourth floor Reactor Building SLC Tank area is _____________________.

A. in service supplied by SGTS B. in service supplied by RBHVAC C. isolated due to loss of Station Air D. not in service due to low IAS pressure Answer: A Answer Explanation SGTS auto starts on RBHVAC isolation at RPV Level 2.

B. is plausible if there is a misconception concerning when RBHVAC isolates.

C & D. are plausible if there is a misconception concerning the effect of loss of Station or Instrument Air systems.

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: 31267 User-Defined ID: R08 Cross Reference Number: NEW Topic: Loss of IAS - RBHVAC Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 doug Comments: KA - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following:

Plant Ventilation ILO EXAM Page: 14 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 8 Table-Item Links Plant Procedures 20.129.01 NUREG 1123 KA Catalog Rev. 2 295019 AK2.08 2.8/2.9 Plant ventilation ILO EXAM Page: 15 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 9 ID: R09 Points: 1.00 The plant is operating in Mode 4 with RHR pump B in Shutdown Cooling. A transient occurs in the plant which results in E1150-F008, RHR SDC outboard isolation valve, failing closed. You have been directed to place a Reactor Recirc pump in service and defeat RWCU isolations.

What is the primary reason for this action?

A. Ensures the necessary pressure head to prevent boiling in the core.

B. Allows for lowering of level to prevent a trip of the SBFW pump.

C. Prevents a RWCU filter demin inlet temperature trip.

D. Provides a means to feed and bleed the Rx vessel.

Answer: D Answer Explanation RHR SDC is lost with the F008 closed. Starting a Recirc pump and defeating RWCU isolations aligns for a feed and bleed control method.

A is a possible misconception of systems used for pressure control.

B Is plausible; SBFW receives an isolation signal for Level 8 signal. SDC is in service with level at or above 220.

C is plausible, but RWCU filter demins do not cause an isolation for high temp.

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: 31468 User-Defined ID: R09 Cross Reference Number: NEW Topic: Shutdown Cooling Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING: Feeding and bleeding reactor vessel ILO EXAM Page: 16 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 9 Table-Item Links Plant Procedures 20.205.01 23.800.04 NUREG 1123 KA Catalog Rev. 2 295021 AK3.02 3.3/3.4 Feeding and bleeding reactor vessel ILO EXAM Page: 17 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 10 ID: R10 Points: 1.00 Fuel Handling operations are in progress, with the Reactor Mode Switch in REFUEL.

The following sequence of events occurs:

00:00 - Drive the refueling bridge from the fuel pool to over a core cell.

00:05 - Lower the Mast from the full up position to the bundle at that core cell.

00:10 - Grapple the fuel bundle.

00:15 - Raise the mast and fuel bundle.

When should a rod withdrawal block first be received during this sequence of events, AND what is the reason for this rod block?

A. 00:00; to prevent inadvertent criticality.

B. 00:05; to prevent inadvertent criticality.

C. 00:00; to prevent unloading a cell with a withdrawn control rod.

D. 00:05; to prevent unloading a cell with a withdrawn control rod.

Answer: B Answer Explanation The purpose of refueling interlocks is to restrict control rod movement, and refueling equipment operation, to reinforce operational procedures that prevent making the reactor critical during refueling. A rod block results when the Mode switch is in REFUEL and the refueling platform is near or over the core and the fuel grapple not full up.

A Is plausible, because the reason for the interlock is to prevent inadvertent criticality.

C Is plausible, because the reason is to prevent inadvertent criticality which occurs at 00:05 D Is plausible, because a rod block first occurs at 00:05.

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: 4.00 System ID: 31529 User-Defined ID: R10 Cross Reference Number: 26603 Topic: Refueling rod blocks Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 13 Text Field: ILO 2013 mike Comments: KA - Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS: Fuel handling equipment ILO EXAM Page: 18 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 10 Table-Item Links Plant Procedures 03D113 NUREG 1123 KA Catalog Rev. 2 295023 AA1.03 3.3/3.6 Fuel handling equipment ILO EXAM Page: 19 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 11 ID: R11 Points: 1.00 The plant is being started after a refueling outage. Reactor power was 9% when a small steam leak developed in the drywell.

The CRS has entered 29.100.01, Sheet 2, Primary Containment Control, based on a high Drywell temperature of 145°F. Drywell pressure is 1.4 psig and rising 0.05 psig every 15 minutes.

What action should be taken in accordance with plant procedures?

A. Start SGTS, and vent the Torus.

B. Place RHR in Torus Cooling and Torus Spray.

C. Verify RBHVAC is running, and vent the Drywell.

D. Scram the reactor in anticipation of an automatic scram.

Answer: C Answer Explanation The EOPs, step PCP-1, direct venting the drywell to keep DW pressure <1.68 psig in accordance with 29.ESP.07.

A. is plausible because a steam leak would indicate particulate in the air. The examinee could expect the vent path to be through SGTS to reduce radioactive release.

B. is plausible because there are elevated containment parameters. The examinee may determine that containment cooling and pressure reduction is necessary at this time.

D.is plausible because the EOPs have been entered. The examinee may deduce that a scram on high drywell is imminent and conservatively scram the reactor. This is not the correct answer because venting the drywell is directed and should allow the operators to perform a controlled shutdown without placing the plant through a scram transient.

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: 4.00 System ID: 32866 User-Defined ID: R11 Cross Reference Number: NEW Topic: Venting DW Pressure Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 Comments: KA - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell pressure ILO EXAM Page: 20 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 11 Table-Item Links Plant Procedures 29.ESP.07 NUREG 1123 KA Catalog Rev. 2 295024 EA2.01 4.2*/4.4* Drywell pressure ILO EXAM Page: 21 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 12 ID: R12 Points: 1.00 The plant is operating at 100% when a circuit card failure results in an uncontrolled lowering of the Reactor Flow Limit. What actions would you be required to take?

A. Lower the pressure regulator setpoint.

B. Place the reactor mode switch in shutdown.

C. Verify the backup pressure regulator takes control.

D. Adjust the turbine flow limiter to match reactor flow limit.

Answer: B Answer Explanation Sudden lowering of the Reactor Flow Limit would result in the reactor pressure regulator system selecting this value through the low value gate logic. RPV pressure will continue to increase, and neither the TCVs nor the BPVs will open.

A. Is plausible, lowering the pressure regulator setpoint would normally cause the control valves to open causing pressure to lower but reactor flow limiter failure would prevent this.

C. Is plausible, would be the action if the pressure regulator fails low.

D. Is plausible, lowering the turbine flow limit would open the bypass valves.

Question 12 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: 31530 User-Defined ID: R12 Cross Reference Number: NEW Topic: Pressure Regulator Failure Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mike Comments: KA - High Reactor Pressure: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

ILO EXAM Page: 22 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 12 Table-Item Links Plant Procedures 03D168 20.000.21 NUREG 1123 KA Catalog Rev. 2 G2.4.49 4.6/4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls 295025 High Reactor Pressure ILO EXAM Page: 23 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 13 ID: R13 Points: 1.00 After a plant transient and reactor scram, the following conditions exist:

Div 1 RHR is injecting with ONE Pump at 13,500 gpm.

Div 1 Core Spray is injecting with TWO Pumps at 7,750 gpm.

Torus Pressure is 3.0 psig.

Torus Level is -70 (minus 70) inches.

Torus Temperature is 180°F.

RPV Pressure is 85 psig (steady).

RPV Water Level is -10 (minus 10) inches (rising).

The NO in the Reactor Building calls to report the RHR and Core Spray Pumps are rattling.

Using current pump configuration, which of the following is the MAXIMUM injection permissible to assure adequate core cooling? (See attached 29.100.01 Sheet 6 curves.)

A. Core Spray Flow - 6,000 gpm; RHR Flow - 8,000 gpm B. Core Spray Flow - 7,000 gpm; RHR Flow - 10,000 gpm C. Core Spray Flow - 7,000 gpm; RHR Flow - 8,000 gpm D. Core Spray Flow - 6,000 gpm; RHR Flow - 10,000 gpm Answer: C Answer Explanation Candidate must apply NPSH and Vortex limits. CS flow is limited by NPSH limit curve, and RHR flow is limited by Vortex limit curve. Torus Overpressure calculates to be 4.2 psig. The RHR vortex limit for -70 is <10,000 gpm, while NPSH is 10,000 gpm.

All distractors are plausible because they contain a violation of one or both curves.

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: 31486 User-Defined ID: R13 Cross Reference Number: 802-3002-0007-050 Topic: ECCS Pump Limit Curves Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 mike Comments: KA - Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Pump NPSH Provide 29.100.01 Sheet 6 without cautions.

ILO EXAM Page: 24 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 13 Table-Item Links Plant Procedures 29.100.01 SH 6 NUREG 1123 KA Catalog Rev. 2 295026 EK1.01 3/3.4 Pump NPSH ILO EXAM Page: 25 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 14 ID: R14 Points: 1.00 Which of the following is a reason why Drywell Sprays are initiated to control Drywell Temperature in the EOPs?

A. Ensures the effects of chugging are avoided.

B. Maintains temperature below Drywell Temperature LCO limits.

C. Maintains temperature within Primary Containment design limits.

D. To ensure RPV water level instrument runs remain below the maximum temperature.

Answer: C Answer Explanation If operation of all available drywell cooling is unable to terminate increasing drywell temperature before applicable component qualification or structural design temperature limits are reached, drywell sprays are initiated to effect the required drywell temperature reduction. This is done through the combined effects of evaporative and convective cooling.

A Is plausible, Drywell sprays are initiated when Suppression Chamber Spray Initiation Pressure is exceeded to preclude chugging.

B Is plausible, Drywell LCO temperature is EOP entry condition.

D Is plausible, EOP sheet 6 caution 1 states water level indications are affected by instrument run temperatures.

Question 14 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: 31533 User-Defined ID: R14 Cross Reference Number: 802-3004-0007-019 Topic: Drywell Spray Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 9 Text Field: ILO 2013 mike Comments: KA - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE: Increased drywell cooling ILO EXAM Page: 26 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 14 Table-Item Links Plant Procedures BWROG EPGs Volume 1 BWROG EPGs Volume 2 NUREG 1123 KA Catalog Rev. 2 295028 EK3.04 3.6/3.8 Increased drywell cooling ILO EXAM Page: 27 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 15 ID: R15 Points: 1.00 RCIC is being used to control RPV Water Level with its suction aligned to the Torus when a leak in the Torus occurs.

Which ONE of the following will occur FIRST as Torus Level continues to lower?

A. RCIC will TRIP due to Low Suction Pressure.

B. RCIC will be manually TRIPPED due to Low Cooling Water Flow.

C. RCIC suction will AUTO TRANSFER to the CST due to Low Suction Pressure.

D. RCIC suction will AUTO TRANSFER to the CST due to Low Torus Water Level.

Answer: A Answer Explanation RCIC will trip on Low Suction Pressure.

B. Is plausible, if low suction pressure trip did NOT occur, RCIC Lube Oil Temperature would rise to a point where equipment damage could occur. No trip on lube oil temperature C. Is plausible, low suction pressure causes a trip, but not a suction transfer to the CST.

D. Is plausible, common misconception may be identified-CST low water level actuates suction transfer to Torus.

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: 2.00 System ID: 31531 User-Defined ID: R15 Cross Reference Number: 315-0143-C002-001 Topic: RCIC Trip Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 mike Comments: KA - Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: RCIC ILO EXAM Page: 28 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 15 Table-Item Links Plant Procedures 01D94 NUREG 1123 KA Catalog Rev. 2 295030 EA1.02 3.4/3.5 RCIC: Plant-Specific ILO EXAM Page: 29 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 16 ID: R16 Points: 1.00 Following a transient, plant conditions are:

Drywell Pressure is 8 psig.

NO High OR Low Pressure Injection systems are running.

Which of the following is the LOWEST stable RPV Water Level which assures Adequate Core Cooling?

A. Top of Active Fuel (TAF)

B. 25 inches BELOW TAF C. 40 inches BELOW TAF D. 48 inches BELOW TAF Answer: C Answer Explanation Minimum Zero Injection Water Level (MZIRWL) defined by the EOP Flowcharts is -40 inches. In the EPGs (App C, pg C-2-53), the MZIRWL is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient steam to prevent any clad temperature in the uncovered part of the core from exceeding 1,800°F. The MZIRWL is determined assuming no water is injected into the RPV.

A is plausible; TAF assures Adequate Core Cooling, but is Not the Lowest level.

B is plausible, and is the lower limit if Injection Systems are operating.

D is plausible if BOTH Core Spray Pumps in one loop are operating.

Question 16 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: 31487 User-Defined ID: R16 Cross Reference Number: 802-3001-0108-001 Topic: ACC water level Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mike Comments: KA - Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: Adequate Core Cooling ILO EXAM Page: 30 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 16 Table-Item Links Plant Procedures 29.100.01 SH 3 BWROG EPG App C NUREG 1123 KA Catalog Rev. 2 295031 EA2.04 4.6*/4.8* Adequate core cooling ILO EXAM Page: 31 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 17 ID: R17 Points: 1.00 A failure to scram (ATWS) has occurred. The following conditions exist:

Forty eight (48) control rods remain partially withdrawn.

Both CRD pumps are operating.

MPUs 2 and 3 are de-energized.

P50-R870 IAS Header Pressure Indicator reads 0 psig.

Which one of the following methods should be attempted to insert the control rods?

A. Manually vent the CRDM over-piston.

B. Scram withdrawn control rods individually.

C. Manually drive withdrawn control rods individually.

D. Defeat RPS and ARI logic, reset the scram, then insert manual scram.

Answer: A Answer Explanation The loss of air prevents resetting scram, and the loss of MPU3 prevents use of RMCS (no rod select power). Venting the over-piston area is the only available option.

B. is incorrect because the rods cannot be individually scrammed if the scram air header cannot be pressurized.

C. is incorrect because no rod select power is available.

D. is incorrect because defeating RPS and ARI logic will not close the scram valves because the loss of air.

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: 4.00 System ID: 31506 User-Defined ID: R17 Cross Reference Number: NEW Topic: ATWS - methods Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mike Comments: KA - SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Generic 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

ILO EXAM Page: 32 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 17 Table-Item Links Plant Procedures 29.ESP.03 NUREG 1123 KA Catalog Rev. 2 G2.4.31 4.2/4.1 Knowledge of annunciators alarms, indications, or response procedures 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or unknown ILO EXAM Page: 33 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 18 ID: R18 Points: 1.00 During an accident condition involving fuel damage and a radiation release, the following conditions exist:

Mode Switch is in SHUTDOWN.

Reactor Power is 12% and oscillating.

Div 1 AXM Channel 4 is 6.0 mCi/cc (rising).

Div 2 AXM Channel 4 is 5.8 mCi/cc (rising).

Why do the EPG BASES permit bypass of the MSIV Level 1 and High Radiation interlocks in this condition?

A. Prevents a threat to Drywell integrity from Hydrogen accumulation.

B. Prevents power oscillations from exceeding the Steam Flow capacity of the Safety Relief Valves.

C. Allows the Main Condenser in conjunction with the Off Gas System to reduce the dose to the public.

D. Allows Main Steam Line Radiation Monitor data to be used to improve the accuracy of Offsite Dose Calculations.

Answer: C Answer Explanation BWROG EPG states: If, instead, high radiation interlocks are not bypassed and steam is discharged through the SRVs into the suppression pool, radionuclides not scrubbed in the pool will accumulate in the containment atmosphere, from which they may escape due to normal containment leakage. Even if processed prior to release by the Standby Gas Treatment System, the public dose will be higher than if these radionuclides were retained in or processed by the Offgas System.

A is plausible; Fuel Damage may be accompanied by Hydrogen generation, which can be a long term containment threat.

B is plausible; other ATWS mitigation actions reduce the probability of fuel damage from core power oscillations.

D is plausible, MSL rad monitor readings are NOT used for offsite dose calculations ILO EXAM Page: 34 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 3.00 System ID: 31507 User-Defined ID: R18 Cross Reference Number: 802-3003-0013-049 Topic: Fuel Damage - Rad release Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mike Comments: KA - Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE:

Protection of the general public Question 18 Table-Item Links Plant Procedures BWROG EPGs Volume 1 NUREG 1123 KA Catalog Rev. 2 295038 EK1.02 4.2*/4.4* Protection of the general public ILO EXAM Page: 35 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 19 ID: R19 Points: 1.00 The plant is operating at rated conditions when a small fire starts around the 2A Transformer.

Which one of the following describes the response of the 2A Transformer Fire Protection System when the 2A Transformer Heat Sensor activates?

A. The Wet Pipe system will only spray when the fusible link melts.

B. Spray will not occur until the 2A Transformer is de-energized by opening breakers CM and CF.

C. Spray will automatically occur, which will result in a subsequent trip of the CM and CF breakers.

D. The deluge valve opens admitting water to the sprinkler piping, but doesn't spray until the fusible link melts.

Answer: B Answer Explanation Transformer Deluge Systems will not actuate unless Transformer Output Breakers are open OR pushbutton on COP is depressed AND any other initiation signal or fault alarm is in.

A. Is plausible, the Deluge system uses open sprinklers instead of fusible sprinklers C. Is plausible, the system will not actuate unless the output breakers are opened.

D. Is plausible, the transformer uses a Deluge Sprinkler System and not the wet pipe fusible link 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: 4.00 System ID: 31532 User-Defined ID: R19 Cross Reference Number: 315-0172-A021-002 Topic: Transformer 2A deluge Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 4 Text Field: ILO 2013 mike Comments: KA - Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Sensors / detectors and valves ILO EXAM Page: 36 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 19 Table-Item Links Plant Procedures 23.501.01 NUREG 1123 KA Catalog Rev. 2 600000 AK2.01 2.6/2.7 Sensors, detectors and valves ILO EXAM Page: 37 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 20 ID: R20 Points: 1.00 RHR pump B is operating in Torus Cooling Mode when a Grid Disturbance occurs. ONLY the 345kV power lines voltage is degrading at 0.3 meter volts per minute.

Which ONE of the following describes the effect, if any, of this voltage degradation?

RHR Pump B ___________________________________________________.

A. breaker will trip on under voltage B. breaker will trip on a degraded voltage load shed C. breaker will trip on overcurrent, due to voltage reduction D. will continue to operate UNAFFECTED for a prolonged period of time due to automatic Load Tap Changer Answer: B Answer Explanation As voltage gradually lowers, the BUS Degraded Voltage condition will occur first thus causing a load shed.

A is plausible, would be true for a rapid grid voltage drop.

C is plausible, as voltage lowers current will rise with constant power.

D is plausible, LTCs are not used on the 345kV side due to the wide fluctuations in voltage.

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: 4.00 System ID: 31526 User-Defined ID: R20 Cross Reference Number: 315-0057-B003-001 Topic: Grid Disturbance Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Knowledge of the interrelations between GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following: Breakers, relays ILO EXAM Page: 38 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 20 Table-Item Links Maintenance Plant Drawings SD-2500-04 I-2572-29 NUREG 1123 KA Catalog Rev. 2 700000 AK2.02 3.1/3.3 Breakers, Relays ILO EXAM Page: 39 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 21 ID: R21 Points: 1.00 The plant is operating at 68% power. Condenser pressure is rising. The current value is 3.0 psia.

At this time, what action should the operator take, and what is the reason for that action?

A. Place additional SJAEs into service to lower condenser pressure.

B. Start an additional Ring Water Buffer Pump to lower condenser pressure.

C. Perform a rapid power reduction to stabilize condenser pressure at 0.7 to 2.5 psia.

D. Place the Reactor Mode Switch to SHUTDOWN to preclude an automatic scram on Main Turbine Trip.

Answer: D Answer Explanation AOP 20.125.01 override states that the Mode Switch is to be placed in Shutdown if condenser vacuum reaches 2.8 psia. The crew will make a conservative decision to shutdown prior to losing the heat sink.

Distractors are plausible in that they are actions that could be taken as condenser pressure rises, but the override takes precedence.

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: 31347 User-Defined ID: R21 Cross Reference Number: NEW Topic: Loss of Vacuum Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 doug Comments: KA - Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM: Loss of Heat Sink ILO EXAM Page: 40 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 21 Table-Item Links Plant Procedures 20.125.01 NUREG 1123 KA Catalog Rev. 2 295002 AK1.03 3.6/3.8 Loss of heat sink ILO EXAM Page: 41 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 22 ID: R22 Points: 1.00 HPCI and RCIC have automatically started following a loss of feedwater event. RPV level rises to 220 inches, and a short time later HPCI turbine speed is 0 RPM. As RPV level begins to lower below 160 inches, the CRS directs HPCI to be restarted.

What MINIMUM action(s) must be taken to restore HPCI injection?

A. Depress the Reactor High Water Level Signal Reset pushbutton.

B. Open E4150-F001, Turbine Steam Supply Isolation Valve and open E4150-F006, HPCI Pump Discharge Outboard Isolation Valve.

C. Depress the Reactor High Water Level Signal Reset pushbutton, and open E4150-F006, HPCI Pump Discharge Outboard Isolation Valve.

D. Open E4150-F003, HPCI Steam Supply Outboard Isolation Valve and open E4150-F006, HPCI Pump Discharge Outboard Isolation Valve.

Answer: C Answer Explanation With no initiation signal present (L2/Hi DW), E4150-F006 will have to be manually opened once the high water level reset is pushed.

A. The L8 reset pushbutton will open the HPCI turbine stop and control valve, but the F006 must be manually opened.

B. E4150-F001 remains open after a L8 trip.

D. E4150-F003 remains open after a L8 trip.

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: 31547 User-Defined ID: R22 Cross Reference Number: 26581 Topic: Loss of Feedwater Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 mike Comments: KA - Ability to operate and/or monitor the following as they apply to HIGH REACTOR WATER LEVEL: HPCI ILO EXAM Page: 42 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 22 Table-Item Links Plant Procedures 23.202 02D089 NUREG 1123 KA Catalog Rev. 2 295008 AA1.04 3.5/3.5 HPCI: Plant-Specific ILO EXAM Page: 43 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 23 ID: R23 Points: 1.00 The plant is operating at 100% power when the following alarms are received:

3D156, REACTOR WATER LEVEL LOW 5D68, RFP LOW FLOW / S RFPT TRIPPED What is the expected response from the Reactor Recirculation system and the basis for that response?

A. Both RR pumps trip to prevent inadvertent power oscillations.

B. RR Pumps run back to Limiter 1 to prevent insufficient subcooling/NPSH loss.

C. RR Pumps run back to Limiter 2/3 to reduce steam flow and water loss from the vessel.

D. RR Pumps continue operating at pre-transient speeds to provide additional heat removal.

Answer: C Answer Explanation RR Limiter 2 is actuated when RPV Level 4 (192.7) alarms and a RFP is tripped or has low suction flow. A runback of Recirculation Pump speed reduces steam flow thus water loss from the vessel. This runback allows the plant time to recover from a tripped feed pump without the reactor scramming on low level.

B Is plausible, RR Limiter 1 is actuated for feed flow less than 20% or Recirculation pump discharge valve not full open.

A Is plausible, Alternate Rod Insertion (ARI) trips both RR MG sets for RPV Level 2.

D Is plausible, misdiagnosed RR response to a RFP trip transient.

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: 2.00 System ID: 31548 User-Defined ID: R23 Cross Reference Number: NEW Topic: RR response Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 3 Text Field: ILO 2013 mike Comments: KA - Knowledge of the interrelations between LOW REACTOR WATER LEVEL and the following: Recirculation system ILO EXAM Page: 44 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 23 Table-Item Links Plant Procedures 20.107.01 20.138.01 NUREG 1123 KA Catalog Rev. 2 295009 AK2.03 3.1/3.2 Recirculation system ILO EXAM Page: 45 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 24 ID: R24 Points: 1.00 What is the basis for the Emergency Operating Procedures requiring Torus and Drywell Sprays to be terminated prior to 0 PSIG?

A. To ensure NPSH limits for ECCS pumps are not violated.

B. To prevent primary containment from becoming de-inerted.

C. To ensure the Drywell Spray Initiation Limit is not exceeded.

D. To prevent the cyclic condensation of steam at the downcomer openings.

Answer: B Answer Explanation The operation of drywell and suppression pool sprays must be terminated by the time drywell pressure and suppression chamber pressure decrease to 0 psig to ensure that primary containment pressure is not reduced below atmospheric. Maintaining a positive suppression chamber pressure precludes air from being drawn in through the vacuum relief system to de-inert the primary containment and also provides a positive margin to the negative design pressure of the primary containment.

A This is a caution associated with reducing Torus pressure thus potentially violating NPSH limits.

C: The DWSIL pressure limitation is 2.68 PSIG and is used for initiation of drywell sprays.

D: This is to preclude the chugging effect associated with the Torus Spray Initiating limit and the basis for starting sprays prior to 9 psig.

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: 31366 User-Defined ID: R24 Cross Reference Number: NEW Topic: Drywell/Torus Spray Termination Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - High Drywell Pressure: Knowledge of the operational implications of EOP warnings, cautions, and notes.

ILO EXAM Page: 46 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 24 Table-Item Links Plant Procedures 29.100.01 SH 6 NUREG 1123 KA Catalog Rev. 2 G2.4.20 3.8/4.3 Knowledge of operational implications of EOP warnings, cautions, and notes 295010 High Drywell Pressure ILO EXAM Page: 47 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 25 ID: R25 Points: 1.00 During a control rod withdrawal, the following indications are received:

3D109 RBM Upscale/Inop 3D113 Control Rod Withdrawal Block White Rod Permissive light OFF Which of the following is the first action directed by plant procedures?

A. Bypass the Rod Block Monitor.

B. Verify thermal limits are acceptable.

C. Deselect, then reselect the selected rod.

D. Ensure the RBM alarm reference point has automatically reset to LOW or MEDIUM.

Answer: B Answer Explanation Both 3D109 and 23.607 directs performance of thermal limit verification prior to moving any other rods.

A. is plausible if examinee thinks RBM malfunction is indicated.

C. is plausible to reset RBM for an edge rod.

D. is plausible but is only required upon start of the unit.

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: 3.00 System ID: 31367 User-Defined ID: R25 Cross Reference Number: NEW Topic: RBM Reset Prereqs Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of the reasons for the following responses as they apply to INADVERTENT REACTIVITY ADDITION: Control Rod Blocks ILO EXAM Page: 48 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 25 Table-Item Links Plant Procedures 23.607 NUREG 1123 KA Catalog Rev. 2 295014 AK3.02 3.7/3.7 Control rod blocks ILO EXAM Page: 49 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 26 ID: R26 Points: 1.00 A system that cannot be isolated from the RPV is discharging outside of the primary containment. The CRS has entered 29.100.01, Sheet 5, Secondary Containment and Rad Release.

Which of the following situations requires that an Emergency Depressurization be performed? (Tables 12 and 14 from EOP 29.100.01, Sheet 5 provided)

A. HPCI/CRD pump area at 220°F with SB HPCI rm at 6 R/hr B. NW RHR pump room at 230°F with SE CS pump rm at 200°F C. SW RHR pump room at 205°F with RBSB SW corner at 5.1 R/hr D. RBSB NE CORNER at 5.3 R/hr with RBSB NW CORNER at 5.1 R/hr Answer: D Answer Explanation Both Rad levels are greater than max safe. This is a valid RO question because ROs are required to know EOP bases.

A/C are incorrect because they each suggest inter-parameter combinations. Their plausibility is based on the fact that they still require an analysis of Table 12 and 14 to draw a proper conclusion.

B is incorrect because SE CS PUMP RM is still below its safe max value. Its plausibility is based on the fact that it still requires an analysis of Table 12 and 14 to draw a proper conclusion.

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: 3.00 System ID: 32886 User-Defined ID: R26 Cross Reference Number: GRAND GULF EXAM BANK (MOD)

Topic: SC rad levels Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mc Comments: KA - Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area radiation levels ILO EXAM Page: 50 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 26 Table-Item Links Plant Procedures 29.100.01 SH 5 NUREG 1123 KA Catalog Rev. 2 295033 EA2.01 3.8/3.9 Area radiation levels ILO EXAM Page: 51 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 27 ID: R27 Points: 1.00 While operating Division 1 SGTS manually for a surveillance, the following indications exist:

SGTS Flow changed from 4100 scfm to 3500 scfm and is lowering slowly SGTS Exhaust Fan is running SGTS Cooling Fan is not running The operator inadvertently depresses the Division 1 Manual isolation pushbutton. Which of the following is the PRIMARY concern for this condition?

A. Reduced flow will lower the resident time in the charcoal filter beds reducing the effectiveness.

B. Reduced flow will raise train temperatures causing reduced train effectiveness.

C. Unless flow is raised, an automatic start of the other division will occur.

D. SGTS may not be able to maintain building differential pressure.

Answer: D Answer Explanation A. Raises residence times B. true but is a very minor if any effect on train effectiveness per design calc DC-0172 C. is not true but if initiating conditions are not well understood could distract D. is true bases for SGTS flow is maintaining building dp post-LOCA.

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: 2.00 System ID: 31406 User-Defined ID: R27 Cross Reference Number: NEW Topic: SC high d/p Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 md Comments: KA - Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: SBGT ILO EXAM Page: 52 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 27 Table-Item Links Plant Procedures 23.404 NUREG 1123 KA Catalog Rev. 2 295035 EA1.02 3.8/3.8 SBGT/FRVS ILO EXAM Page: 53 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 28 ID: R28 Points: 1.00 (1) Which of the following is the method used by RHR LPCI mode to assure adequate core cooling and (2) which limit will ensure peak cladding temperatures will not be exceeded during a LOCA?

A. (1) steam cooling (2) Minimum Critical Power Ratio (MCPR)

B. (1) core submergence (2) Average Planar Linear Heat Generation Rate (APLHGR)

C. (1) core submergence (2) Linear Heat Generation Rate (LHGR)

D. (1) steam cooling (2) Average Planar Linear Heat Generation Rate (APLHGR)

Answer: B Answer Explanation RHR injection, along with jet pump configuration, is used to fill the RPV to cover the core during a LOCA. APLHGR is a function of reactor power, core flow, fuel type, and average planar exposure. The limit is developed, using NRC approved methodolgy to ensure gross cladding failure will not occur following a loss of coolant accident (LOCA).

Plausible Distractors:

A - other method used to assure ACC, but not the method used by RHR LPCI. MCPR applies to normal power operation and transients, not accident conditions.

C - correct method used to assure ACC, but not the limit to ensure peak cladding will not be exceeded.

D - other method used to assure cooling, but not the method used by RHR LPCI.

Question 28 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: 31407 User-Defined ID: R28 Cross Reference Number: NEW Topic: LPCI - ACC Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 Comments: KA - Knowledge of the operational implications of the following concepts as they apply to RHR/LPCI: INJECTION MODE (PLANT SPECIFIC): Core cooling methods ILO EXAM Page: 54 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 28 Table-Item Links Plant Procedures 23.205 TECH SPECS NUREG 1123 KA Catalog Rev. 2 203000 K5.02 3.5/3.7 Core cooling methods ILO EXAM Page: 55 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 29 ID: R29 Points: 1.00 The plant has been shutdown for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following 300 days of power operation with the following conditions:

RHR Pump C is operating in Shutdown Cooling Mode.

RHRSW Pumps A AND C are supplying the Div 1 RHR Heat Exchanger.

RPV Level is 230 inches.

Which of the following actions should be taken for an over-current trip of RHRSW Pump C?

A. Throttle closed E1150-F068A, Div 1 RHR HX Serv WTR Outlet FCV, to establish proper RHRSW flow AND enter 20.205.01, Loss of Shutdown Cooling.

B. Throttle open E1150-F068A, Div 1 RHR HX Serv WTR Outlet FCV, to maximize service water flow AND cross tie RHRSW per 23.208, RHR Complex Service Water System.

C. Fully close E1150-F048A, RHR Heat Exchanger Bypass Valve, to increase heat exchanger load AND establish decay heat removal per 23.800.05, Alternate Remote Coolant Circulation and Decay Heat Removal.

D. Fully open E1150-F048A, RHR Heat Exchanger Bypass Valve, to reduce heat exchanger load AND establish decay heat removal per 23.800.05, Alternate Remote Coolant Circulation and Decay Heat Removal.

Answer: A Answer Explanation Correct Answer A. RHRSW valve is throttled closed to meet pump DP requirements. Both RHRSW pumps are needed for SDC per 20.205.01 Plausible Distractors:

ALT Decay Heat removal procedures are plausible and directed from Loss of SDC AOP.

Throttling open valves will increase flow but is not done to keep pump in the operating band.

ILO EXAM Page: 56 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 3.00 System ID: 35546 User-Defined ID: R29 Cross Reference Number: 315-0168-C005-002 Topic: Shutdown Cooling Cooldown Rate Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 Comments: KA - Knowledge of the effect that a loss or malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Component cooling water systems Question 29 Table-Item Links Plant Procedures 23.208 NUREG 1123 KA Catalog Rev. 2 205000 K6.05 3.2/3.3 Component cooling water systems ILO EXAM Page: 57 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 30 ID: R30 Points: 1.00 At 100% power a valid high drywell pressure signal occurs due to a small instrument line break concurrent with a MSIV isolation.

With reactor pressure reading 1134 psig (1) What is the status of HPCI 60 seconds after receiving the high drywell pressure signal and (2) what operator action must be taken?

A. (1) Running and discharging through the minimum flow line (2) Trip the HPCI turbine B. (1) Running and injecting to the vessel at 5200 gpm (2) Verify adequate feed flow and dial HPCI controller to minimum C. (1) Running and injecting to the vessel at 5200 gpm (2) Trip the HPCI turbine D. (1) Running and discharging through the minimum flow line (2) Verify adequate feed flow and dial HPCI controller to minimum Answer: B Answer Explanation The system will start normally and inject. The reactor pressure encompassing HPCI System Operation is 1169 psig max. The Fermi IST program controls the actual system response time below 55 seconds to ensure it remains within the 60-second maximum analyzed value.

A. is plausible because HPCI starts on Hi DW. The examinee may believe it will be on min flow because reactor pressure is at 1134 psig and HPCI may not be up to speed within 60 seconds. Also, they may trip the turbine because the turbine is not needed.

C. is plausible because they may decide to trip the turbine because it is not needed for RPV water level control. The correct action is to throttle flow to maintain level in band and shutdown iaw the SOP if it is not needed.

D. is plausible because HPCI starts on Hi DW. The examinee may believe it will be on min flow because reactor pressure is at 1134 psig and HPCI may not be up to speed within 60 seconds.

ILO EXAM Page: 58 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 3.00 System ID: 31427 User-Defined ID: R30 Cross Reference Number: NEW Topic: HPCI start signals Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 Comments: KA - Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High drywell pressure Question 30 Table-Item Links Plant Procedures 23.202 NUREG 1123 KA Catalog Rev. 2 206000 A2.16 4/4.1 High drywell pressure: BWR-2,3,4 Design Basis Documents E41-00 High Pressure Coolant Injection System ILO EXAM Page: 59 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 31 ID: R31 Points: 1.00 While operating at 100% power, with EDG # 11 out of service, a Recirculation Loop rupture occurs. This is followed by a loss of Bus 64B.

What is the impact of this electrical loss?

A. Core Spray Pump A is de-energized.

B. Core Spray Pump B is de-energized.

C. RHR Pump C is de-energized.

D. RHR Pump D is de-energized.

Answer: A Answer Explanation Only Core Spray Pump A is powered from 4160v Bus 64B.

B. Is plausible, CS pump B is powered from 4160v Bus 65E C. Is plausible, RHR pump C is powered from 4160v Bus 64C D. Is plausible, RHR pump D is power from 4160v Bus 65F Question 31 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: 31428 User-Defined ID: R31 Cross Reference Number: NEW Topic: Core Spray Power Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of electrical power supplies to the following:

Pump power Question 31 Table-Item Links Plant Procedures 23.203 NUREG 1123 KA Catalog Rev. 2 209001 K2.01 3.0*/3.1* Pump power ILO EXAM Page: 60 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 32 ID: R32 Points: 1.00 The reactor is operating at 68% power when a LOCA occurs with a Lockout of Bus 65F. The following conditions exist:

Reactor power all rods in RPV pressure 452 psig (slowly lowering)

RPV water level 112 inches (rising)

Drywell pressure 7 psig (rising)

Which ONE of the following would be correct for the Core Spray System?

A. Core Spray Pump C is operating , E2150-F004A DIV 1 CS OTB ISOL VLV open and E2150-F005A DIV 1 CS INBD ISOL VLV is closed.

B. Core Spray Pumps B and D are operating , E2150-F004B DIV 2 CS OTBD ISOL VLV and E2150-F005B DIV 2 CS INBD ISOL VLV are open.

C. Core Spray Pumps A and C are operating , E2150-F004A DIV 1 CS OTBD ISOL VLV and E2150-F005A DIV 1 CS INBD ISOL VLV are open.

D. Core Spray Pump B is operating , E2150-F004B DIV 2 CS OTB ISOL VLV open and E2150-F005B DIV 2 CS INBD ISOL VLV open.

Answer: C Answer Explanation 461psig is the reactor low pressure alarm 2D27 which opens the E2150-F005A/B INBD isolation valve. The lock out of 65F results in loss of power to CS pump D and the closed E2150-F005B.

A. Is plausible, the E2150-F005A opens at reactor pressure 461 psig.

B. Is plausible, CS pump D has no power as a result of 65F bus lockout.

D. Is plausible, the E2150-F005B has no power as a result of bus lockout.

Question 32 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: 35446 User-Defined ID: R32 Cross Reference Number: 202-0501-A003-050 Topic: Core Spray Injection Pressure Status Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 Mike Comments: KA - Ability to predict and/or monitor changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including: Reactor pressure ILO EXAM Page: 61 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 32 Table-Item Links Plant Procedures 02D027 NUREG 1123 KA Catalog Rev. 2 209001 A1.04 3.7/3.7 Reactor pressure ILO EXAM Page: 62 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 33 ID: R33 Points: 1.00 The plant has experienced an ATWS condition, and SLC injection has been directed.

Which RWCU valve isolations should be expected following SLC Pump starting?

A. G3352-F001, RWCU Supply Inbd Iso Vlv, and G3352-F004, RWCU Supply Otbd Iso Vlv B. G3352-F001, RWCU Supply Inbd Iso Vlv, and G3352-F220, RWCU to FW Otbd Cntm Iso Vlv C. G3352-F004, RWCU Supply Otbd Iso Vlv, and G3352-F220, RWCU to FW Otbd Cntm Iso Vlv D. G3352-F001, RWCU Supply Inbd Iso Vlv, and G3352-F004, RWCU Supply Otbd Iso Vlv, and G3352-F220, RWCU to FW Otbd Cntm Iso Vlv Answer: C Answer Explanation Correct Answer C - When the SLC actuation switched is placed in A(B) RUN, G3352-F004 closes and the RWCU Pumps trip, and G3352-F220 closes.

Plausible Distractors:

A - are plausible, but G3352-F001 only closes when a RWCU System isolation is received.

B - are plausible, but G3352-F001 only closes when a RWCU System isolation is received.

C - are plausible, but G3352-F001 only closes when a RWCU System isolation is received.

Question 33 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: 31430 User-Defined ID: R33 Cross Reference Number: NEW Topic: SLC injection indications Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 doug Comments: KA - Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: RWCU isolation ILO EXAM Page: 63 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 33 Table-Item Links Plant Procedures 23.139 NUREG 1123 KA Catalog Rev. 2 211000 K4.07 3.8*/3.9* RWCU isolation ILO EXAM Page: 64 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 34 ID: R34 Points: 1.00 Reactor power is stable at 100% when 3D11, SLC Continuity Loss, alarms. The operator dispatched to H11-P613 reports that Squib Valve Currents are C41-M600A reading 5 ma, and C41-M600B reading 0 ma.

Based on these indications, which one of the following statements is true?

A. Squib A indicating light is OFF.

B. Squib B indicating light is OFF.

C. Both Squib indicating lights are ON.

D. Both Squib indicating lights are OFF.

Answer: B Answer Explanation Correct Answer B - Squib current reading should correspond to the indicating light on P603.

When the light is ON, current should be ~5ma. The light is OFF when current is <2ma.

Plausible Distractors:

A - are plausible if examinee is confused about the correlation of current readings to light indication.

C - are plausible if examinee is confused about the correlation of current readings to light indication.

D - are plausible if examinee is confused about the correlation of current readings to light indication.

Question 34 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: 31431 User-Defined ID: R34 Cross Reference Number: NEW Topic: SLC inop Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including: Explosive valves indicating lights ILO EXAM Page: 65 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 34 Table-Item Links Plant Procedures 03D011 NUREG 1123 KA Catalog Rev. 2 211000 A3.03 3.8/3.8 Explosive valves indicating lights: Plant-Specific Technical Specifications 3.1.7 Standby Liquid Control (SLC) System ILO EXAM Page: 66 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 35 ID: R35 Points: 1.00 Which of the following combinations result in a Reactor Scram?

A. RPV Pressure instruments B21N078A and C upscale high B. MSL Radiation Monitor channels D11K603B and D upscale C. IRM A is INOP with IRM H reading 121 (Range 4) with Mode Switch not in RUN D. IRM E reads 36 (Range 5) with IRM H reading 121 (Range 6) with Mode Switch not in RUN Answer: C Answer Explanation C IRM A in INOP provides a trip signal to trip channel A1 and IRM H reading higher then 120 on 125 scale will produce a trip signal to trip channel B2. With Mode Switch not in RUN will trip both RPS logics for a full scram.

A RPV Pressure instruments B21-N078A and C are both in the same trip system and will only cause a half scram.

B MSL Rad Monitors D11-K603B and D are both in the same trip system and will only cause a half scram.

D IRM E reading 36 on range 5 does not meet the comparable ratio of 120 on 125 scale (96%)

for 0-40 and will only cause a half scram for the IRM H upscale trip.

Question 35 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: 31432 User-Defined ID: R35 Cross Reference Number: NEW Topic: RPS logic Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM:

Specific logic arrangements ILO EXAM Page: 67 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 35 Table-Item Links Plant Procedures 23.601 NUREG 1123 KA Catalog Rev. 2 212000 K5.02 3.3/3.4 Specific logic arrangements ILO EXAM Page: 68 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 36 ID: R36 Points: 1.00 The plant is operating at 100% power when a rupture in the Reactor Feed pump control oil system results in a trip of the North Reactor Feed pump. Without any operator action, which of the following explains the resultant plant response?

A. At 173 inches the reactor scrams with level dropping to approximately 140 inches and returns to approximately 197 inches. Reactor power drops with a stable -80 second period.

B. At 173 inches the reactor scrams with level dropping to 110 inches with HPCI and RCIC auto starting and recovering level. Reactor power drops with a stable -80 second period.

C. Both Reactor Recirculation pumps run back to limiter 2/3 setting of 37% speed. Reactor power decreases to approximately 66%.

D. Both Reactor Recirculation pumps run back to limiter 2/3 setting of 39% speed. Reactor power decreases to approximately 76%.

Answer: C Answer Explanation A trip of a Reactor Feed pump will result in a runback to limiter 2/3 with a power drop to approximately 66%

Plausible Distractors:

A Is plausible, a trip of one RFP does not result in RPV level dropping to the SCRAM setpoint.

B Is plausible, a trip of one RFP does not result in RPV level dropping to the SCRAM setpoint nor auto start of HPCI or RCIC D . Is plausible, the 2/3 limiter set point is 37% while the manual runback is 39%. With the runback, power will be less than 76%.

Question 36 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: 35466 User-Defined ID: R36 Cross Reference Number: MODIFIED FROM CGS ILO EXAM Topic: RFP Trip Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 5 Text Field: ILO 2013 Mike Comments: KA - Ability to manually operate and/or monitor in the control room: Reactor power ILO EXAM Page: 69 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 36 Table-Item Links Plant Procedures 23.138.01 Simulator NUREG 1123 KA Catalog Rev. 2 212000 A4.05 4.3*/4.3* Reactor power ILO EXAM Page: 70 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 37 ID: R37 Points: 1.00 A reactor start up is in progress with power ascending through the Intermediate range and a heatup rate being established when 3D64, IRM Downscale, alarms.

In accordance with 23.603, the P603 operator should ____________________.

A. bypass the associated IRM B. notch Control Rods to keep IRM on scale C. range the associated IRM to next lower range D. wait until rising reactor power causes the downscale alarm to clear Answer: C Answer Explanation Correct Answer - During reactor startup while power is ascending through the Intermediate range, avoid ranging down IRM's unless 3D64, "IRM DOWNSCALE" is received for the IRM downscale.

Plausible Distractors:

A. Is plausible, would be performed if down range was unsuccessful.

B. Is plausible, notching control rods would bring the IRM back on scale.

D. Is plausible,waiting for power to increase would clear the alarm but is not procedurally driven.

Question 37 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: 31270 User-Defined ID: R37 Cross Reference Number: NEW Topic: Startup - IRMs Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 6 Text Field: ILO 2013 Comments: KA - Intermediate Range Monitor (IRM) System: Ability to interpret and Execute Procedure Steps ILO EXAM Page: 71 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 37 Table-Item Links Plant Procedures 23.603 NUREG 1123 KA Catalog Rev. 2 G2.1.20 4.6/4.6 Ability to interpret and execute procedure steps 215003 IRM System ILO EXAM Page: 72 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 38 ID: R38 Points: 1.00 The reactor operator is inserting a control rod to lengthen reactor period during a reactor startup. The IRM channels are on Range 3. The reactor mode switch is in STARTUP and no SRM channels are bypassed.

What is the effect if SRM A malfunctions and fails high?

A. The Reactor Scrams.

B. Rod motion is blocked.

C. Rod motion may continue.

D. A Half Scram is received on RPS A.

Answer: C Answer Explanation The shorting links are only removed during fuel/handling evaluations. A rod withdrawal block would be actuated for any rod being withdrawn. This rod is being inserted.

A. Is plausible, would be true if shorting links were removed B. Is plausible, this would be true for any rod being withdrawn D. Is plausible, SRM A Upscale Trip contact feeds into Trip Logic A1.

Question 38 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: 31566 User-Defined ID: R38 Cross Reference Number: 315-0122-0004-005 Topic: SRM malfunction Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 2 Text Field: ILO 2013 mike Comments: KA - Knowledge of the physical connections and/or cause effect relationships between SOURCE RANGE MONITOR (SRM)

SYSTEM and the following: Reactor Protection System ILO EXAM Page: 73 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 38 Table-Item Links Plant Procedures 23.602 NUREG 1123 KA Catalog Rev. 2 215004 K1.01 3.6/3.7 Reactor protection system ILO EXAM Page: 74 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 39 ID: R39 Points: 1.00 The plant is operating at 100% power when 9D70, DIV 1 120V RPS BUS 1A POWER FAILURE, alarms.

What affect will this condition have on the Average Power Range Monitors (APRMs)?

A. APRMs will remain energized.

B. APRM channel 1/3 will be INOP.

C. Control Rod Block AND APRM Upscale will alarm.

D. APRM 1/3 Simulated Thermal Power output fails low.

Answer: A Answer Explanation Power is auctioneered such that a loss of RPS power results in the APRM, LPRM and RBM remaining energized and functional.

B is plausible, APRMs 1/3 receive primary power through RPS A.

C is plausible, but ONLY partially correct, Control Rod Block will occur but APRMs remain powered through QLVPS and upscale will not occur.

D is plausible, APRMs will remain powered through auctioneered power via RPS B.

Question 39 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: 31567 User-Defined ID: R39 Cross Reference Number: NEW Topic: APRM - power supply Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 6 Text Field: ILO 2013 mike Comments: KA - Knowledge of electrical power supplies to the following:

APRM channels ILO EXAM Page: 75 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 39 Table-Item Links Plant Procedures 23.605 09D70 NUREG 1123 KA Catalog Rev. 2 215005 K2 02 2.6/2.8 APRM channels ILO EXAM Page: 76 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 40 ID: R40 Points: 1.00 The reactor is operating with both recirculation loops in operation when a manual runback is performed resulting in the following conditions:

APRM Flux is 73%.

APRM Recirc Flow is 40%.

Total Core Flow is 54 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. 85%

B. 87%

C. 96%

D. 113.5%

Answer: B Answer Explanation Justification: The APRM Simulated Thermal Power Trip Setpoint is 0.63 (W) + 61.4% with W=40, the Trip Setpoint is 86.6%. The lowest listed power which exceeds this is 87%.

A Is plausible, misunderstanding of how trip setpoints work C Is plausible, and is miscalculated with W=54 (core flow)

D Is plausible, 113.5% is the high clamp value for the APRM STP trip Setpoint Question 40 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: 31527 User-Defined ID: R40 Cross Reference Number: NEW Topic: APRM Trip setpoint Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

Core flow effects on APRM trip setpoints No reference will be provided.

ILO EXAM Page: 77 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 40 Table-Item Links Plant Procedures 03D101 NUREG 1123 KA Catalog Rev. 2 215005 K5.05 3.6/3.6 Core flow effects on APRM trip setpoints ILO EXAM Page: 78 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 41 ID: R41 Points: 1.00 While operating at 100% CTP, a Station Blackout occurs.

Div 1 ESF batteries experience a fault, and Div 1 DC distribution is LOST.

1D56, RCIC LOGIC BUS POWER FAILURE, alarms.

Which statement below describes the effect that the loss of Div 1 ESF DC distribution has on level control?

A. All injection sources will be lost.

B. Fire Header must be used to maintain level.

C. HPCI system must be used to control RPV level.

D. RCIC can be used for injection but must be controlled from the Control Room.

Answer: C Answer Explanation HPCI is powered from Div 2 DC. RCIC is powered from Div. 1.

A Is plausible, SBO results in limited injection sources B Is plausible, HPCI is available for injection.

D Is plausible, under certain logic failures RCIC will still function Question 41 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: 31568 User-Defined ID: R41 Cross Reference Number: 315-0143-A014-004 Topic: RCIC-SBO Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on following: Reactor water level ILO EXAM Page: 79 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 41 Table-Item Links Plant Procedures 20.300.SBO 01D56 NUREG 1123 KA Catalog Rev. 2 217000 K3.01 3.7/3.7 Reactor water level ILO EXAM Page: 80 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 42 ID: R42 Points: 1.00 A plant transient has occurred, and ADS was allowed to automatically initiate. The following plant conditions exist:

Drywell pressure 1.6 psig (lowering)

RPV pressure 724 psig (lowering)

RPV water level 28 inches (lowering)

RHR Pumps all running Core Spray Pumps all running ADS initiated Given the above conditions, which of the following actions would cause the ADS valves to close?

A. Recovering RPV level above Level 1 B. Depressing the ADS Timer Logic reset pushbuttons C. Placing the ADS Inhibit Switches to the "Inhibit" position D. Depressing the ADS Initiation Drywell High Pressure Reset pushbutton Answer: B Answer Explanation Depressing the ADS timer reset pushbuttons will deenergize the K6B/K7B relays, reseting ADS logic, causing the ADS valves to close.

All distractors show a misunderstanding of ADS logic.

Question 42 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: 31569 User-Defined ID: R42 Cross Reference Number: 315-0142-0004-003 Topic: ADS Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which provide for the following: ADS logic control ILO EXAM Page: 81 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 42 Table-Item Links Plant Procedures 23.601 23.201 NUREG 1123 KA Catalog Rev. 2 218000 K4.03 3.8/4 ADS logic control ILO EXAM Page: 82 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 43 ID: R43 Points: 1.00 The plant is operating at power when it is discovered that a mis-calibrated instrument was used to set the High Drywell Pressure instrumentation setpoint. Which of the following Group isolations would be impacted by this error?

Group 1 - MSIV & Drains Group 10 - RWCU Inbd Group 2 - Rx Sample Group 11 - RWCU Outbd Group 3 - RHR Group 12 - TWMS Group 4 - SDC/HD Spray Group 13 - DW Sumps Group 5 - CSS Group 14 - PC Vent Group 6 - HPCI Group 15 - TIP Group 7 - HPCI Vac Bkr Group 16 - PC Press Cont Group 8 - RCIC Group 17 - RRS Seals/PCRMS Isol Group 9 - RCIC Vac Bkr Group 18 - DW Pneumatics A. Groups 1,3,7,9,12,13,14,15,18, B. Groups 2,3,7,9,11,12,13,14,15,18 C. Groups 2,3,5,7,9,12,13,14,15,16,17,18 D. Groups 2,4,5,7,9,12,13,14,15,16,17,18 Answer: C Answer Explanation The automatic closure of various Class B valves prevents the release of significant radioactive material from the Primary Containment. These valves are not needed for a safe shutdown of the plant.

A. is incorrect; MSIV and drains will not isolate on a high drywell pressure signal.

B. is incorrect; RWCU will not isolate on drywell pressure.

D. is incorrect; SDC/HD Spray will not isolate on drywell pressure.

ILO EXAM Page: 83 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 6 Difficulty: 4.00 System ID: 31570 User-Defined ID: R43 Cross Reference Number: NEW Topic: Group isolation - Drywell pressure Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Containment instrumentation Question 43 Table-Item Links Plant Procedures 23.427 29.ESP.01 NUREG 1123 KA Catalog Rev. 2 223002 K6.05 3.0/3.3 Containment instrumentation ILO EXAM Page: 84 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 44 ID: R44 Points: 1.00 RCIC Steam Line Pressure - Low signals have been received from the following instruments:

E5150-N058A E5150-N058B E5150-N058C Based on these signals, what is the status of RCIC?

A. In a normal standby lineup.

B. Isolated with ONLY the E5150-F007, RCIC Steam Line Inboard Valve, shut.

C. Isolated with ONLY the E5150-F008, RCIC Steam Line Outboard Valve, shut.

D. Isolated with both E5150-F007, RCIC Steam Line Inboard Valve, and E5150-F008, RCIC Steam Line Outboard Valve, shut.

Answer: C Answer Explanation The trip of instruments A & C causes the closure of E5150-F008.

A. is incorrect since the trip of A & C or B & D would cause a valve closure.

B. is incorrect since B & D would have to be tripped to close E5150-F007.

D. is incorrect since all 4 instruments would have to be tripped to close both E5150-F007 and F008.

Question 44 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 4.50 System ID: 31287 User-Defined ID: R44 Cross Reference Number: NEW Topic: PCIS - RCIC Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including: Valve Closures ILO EXAM Page: 85 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 44 Table-Item Links Plant Procedures 23.601 NUREG 1123 KA Catalog Rev. 2 223002 A1.02 3.7/3.7 Valve closures ILO EXAM Page: 86 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 45 ID: R45 Points: 1.00 During normal power operation an SRV fails open. Why does Feed Water Level Control maintain RPV water level at a different level until the SRV is closed?

A. Feedwater flow rises, but not enough to compensate for the additional steam loss.

B. Feedwater flow lowers to anticipate level swell.

C. Feedwater flow rises to match actual steam flow.

D. Feedwater flow lowers to match indicated steam flow.

Answer: D Answer Explanation Since FW Control does not sense the SRV steam flow, indicated steam flow lowers. FW Control reduces feed flow to match indicated steam flow. This results in RPV level lowering. The lower RPV level creates a level deviation, and feed flow is raised until RPV level is stable, but at a lower level than before the transient.

A. This is a plausible condition but feedwater flow would lower to match indicated steam flow B. This is a plausible condition but feedwater flow would lower due to level swell and lower indicated steam flow C. This is a plausible condition but steam flow thru SRV is not seen by Feedwater Control System Question 45 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: 31626 User-Defined ID: R45 Cross Reference Number: NEW Topic: SRV indications Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 5 Text Field: ILO 2013 doug Comments: KA - Ability to predict and/or monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including: Indicated vs. actual steam flow ILO EXAM Page: 87 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 45 Table-Item Links Plant Procedures 23.107 20.000.25 NUREG 1123 KA Catalog Rev. 2 239002 A1.09 3.1/3.3 Indicated vs. actual steam flow: Plant-Specific ILO EXAM Page: 88 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 46 ID: R46 Points: 1.00 With reactor power at 100%, the RFP A controller shifts to EMERGENCY BYPASS mode.

How does RPV level respond, and what actions are needed to restore level control?

A. Level lowers. Lower recirc flow and insert cram array to allow capacity of feedwater to turn level.

B. Level lowers. Take manual control of RFP A and RFP B to raise Feed Flow and restore level.

C. Level will not change. Take manual control of RFP A, and control speed allowing RFP B to control level as necessary.

D. Level will not change. Take manual control of RFP B, and monitor for changes continuously until controller is repaired.

Answer: C Answer Explanation Level does not change. AOP 20.107.01 directs placing the affected RFP (A) to manual, and controlling speed as necessary to allow unaffected RFP (B) to control level.

A. Functional misconception - RFP will not lose signal, if it did this would be appropriate B. Functional misconception - RFP will not lose signal so level will not lower, controller in manual D. Functional misconception - Incorrect action, unaffected RFP should remain in auto Question 46 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: 31627 User-Defined ID: R46 Cross Reference Number: NEW Topic: DCS Failure Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 doug Comments: KA - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of controller signal output ILO EXAM Page: 89 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 46 Table-Item Links Plant Procedures 20.107.01 23.107 NUREG 1123 KA Catalog Rev. 2 259002 A2.06 3.3/3.4 Loss of controller signal output ILO EXAM Page: 90 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 47 ID: R47 Points: 1.00 SGTS has started on an automatic signal. SGTS D1 flow is 1600 scfm, and 8D35, DIV 1 SGTS Air Flow Stopped, has alarmed.

Low air flow could be caused by which of the following?

A. Div 1 SGTS 24kW Heater tripped.

B. SGTS Pre-Filter differential pressure is 1.3 water gauge.

C. Breaker for T46-C003, Div 1 SGTS Exhaust Fan has tripped.

D. T46-F003A, Div 1 SGTS Exhaust Fan Inlet Vortex Damper, malfunctioning.

Answer: D Answer Explanation SGTS Exhaust Fan Inlet Vortex Damper modulates on start to maintain normal flow band. A malfunction could cause it to maintain a lower than normal flow.

Plausible Distractors A. heater will trip on alarm. If water collects in the charcoal could restrict flow.

B. could lower flow, but vortex damper would maintain flow.

C. if exhaust fan trips, flow would be 0.

Question 47 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: 31628 User-Defined ID: R47 Cross Reference Number: NEW Topic: SGTS malfunction Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Valve operation ILO EXAM Page: 91 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 47 Table-Item Links Plant Procedures 08D35 23.404 NUREG 1123 KA Catalog Rev. 2 261000 A3.03 3/2.9 Valve operation ILO EXAM Page: 92 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 48 ID: R48 Points: 1.00 Maintenance has completed work on Bus 72S alternate supply breaker, 72S Pos 1C. Post maintenance testing has been completed and the breaker has been released for service. A failure causes 72S Pos 1B, Bus 72S normal supply breaker, to trip OPEN. The following indications are observed:

72S Pos 1B Indicates closed 72S Pos 1C Indicates tripped 9D16, DIV I 480V ESS BUS 72 BKR TRIPPED In alarm 72S Bus Voltage Zero (0)

What has occurred to cause these indications?

A. 72S auto throw-over worked properly.

B. Breaker 72S Pos 1C was left in TEST position.

C. Bus 72S throw-over mode select switch is in MANUAL.

D. A fault on bus 72S prevented energizing from the alternate supply.

Answer: B Answer Explanation From 23.300, TEST - This position is used for testing a circuit breaker for proper operation. In this position, the main contacts are separated from the supply and load. The control circuit and auxiliary control are operational.

The normal control circuitry would energize the closing coil causing the breaker to close. The normal closed indications would be observed in the control room. The bus would not be powered because the main contacts would still be open.

A. is plausible because 72S Pos 1C indicates CLOSED. The examinee may not understand that the bus voltage is from the bus and not independent from breaker position.

C. is plausible because there is an apparent failure of the alternate supply to power the bus based on Zero bus voltage. The throw over switch in MANUAL would prevent auto throw over.

D. is plausible because some buses have lock out features that prevent energizing from another source if there is a fault on the bus.

ILO EXAM Page: 93 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 3.00 System ID: 31646 User-Defined ID: R48 Cross Reference Number: NEW Topic: 72S Pos 1C in TEST Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Ability to manually operate and/or monitor in the control room: All breakers and disconnects (including available switch yard)

Question 48 Table-Item Links Plant Procedures 09D16 23.300 NUREG 1123 KA Catalog Rev. 2 262001 A4.01 3.4/3.7 All breakers and disconnects (including available switch yard): Plant-Specific ILO EXAM Page: 94 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 49 ID: R49 Points: 1.00 The Rectifier/Charger and DC battery become disconnected from UPS Unit A due to a fault. Loads on UPS A Distribution cabinets are ________________________.

A. lost due to the loss of battery back-up B. not affected due to static transfer switch operation C. lost due to failure of Rectifier/Charger causing internal AC loss D. not affected since Bus 72M pos. 3D (Normal) is still energized Answer: B Answer Explanation Correct Answer B - If all DC power is lost to a UPS unit, Static Transfer Switch operation will automatically supply the distribution cabinet on that side from the alternate power supply.

Plausible Distractors:

A & C are incorrect since Static Transfer Switch functions to maintain loads.

D is incorrect because AC supply to the rectifier is deenergized.

Question 49 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 4.00 System ID: 31648 User-Defined ID: R49 Cross Reference Number: NEW Topic: UPS faults Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Uninterruptable Power Supply (A.C./D.C.): Generic Ability to determine operability and/or availability of safety related equipment ILO EXAM Page: 95 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 49 Table-Item Links Plant Procedures 23.308.01 NUREG 1123 KA Catalog Rev. 2 G2.2.37 3.6/4.6 Ability to determine operability and/or availability of safety related equipment 262002 UPS (AC/DC)

ILO EXAM Page: 96 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 50 ID: R50 Points: 1.00 The plant is operating at 100% power with the AC Distribution System aligned normally. Loss of Battery 2B-2 results in a loss of control power to 480v ESF Bus 72F. Which of the following would be the impact of this condition?

A. 480v MCC 72CF transfers to Alternate.

B. North RWCU Pump trips and the system isolates.

C. Power is lost to Division 2 SGTS fans and dampers.

D. The automatic throw-over function of 480v MCC 72CF is disabled.

Answer: D Answer Explanation 20.300.72F, Caution 2, states "Loss of Div 2 Battery 2B-2 results in loss of control power to Bus 72F which prevents auto transfer of MCC 72CF, and requires compliance with Technical Specifications."

Plausible Distractors:

A. would be true if 72CF was aligned to 72F (72C normally).

B. is incorrect since N RWCU Pump is not affected by the DC loss and is powered from 72C which is still energized.

C. is incorrect since Div 2 SGTS is not affected by the DC loss and is powered from 72F which is still energized.

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: 4.00 System ID: 31666 User-Defined ID: R50 Cross Reference Number: NEW Topic: DC distribution Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following: A.C. electrical distribution ILO EXAM Page: 97 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 50 Table-Item Links Plant Procedures 20.300.72F NUREG 1123 KA Catalog Rev. 2 263000 K1.01 3.3/3.5A.C. electrical distribution ILO EXAM Page: 98 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 51 ID: R51 Points: 1.00 The plant is operating at 100% power. EDG 12 is running paralleled to Bus 64C for a surveillance run.

The following events then occur:

9D15, D1 4160V ESS Bus 64C Breaker Tripped, alarms.

64C-Pos.C6 trips open.

64C-Pos.C8 trips open.

Bus 64C power ON light goes OFF.

Based on these indications which of the following is true?

A. RBCCW is not affected.

B. North RRMG Set scoop tube positioner is locked.

C. CRS should enter 20.307.01, Emergency Diesel Generator Failure.

D. A half scram is received on Division 1 if RPS A is on normal supply.

Answer: B Answer Explanation 20.300.64C, Note 8 states "The North RR MG Scoop Tube Positioner will automatically lock on loss of power to the Scoop Tube Positioner and due to MPU 4 transfer."

A. N RBCCW pump is powered from 72C.

C. not appropriate as bus has tripped; not an EDG issue.

D. RPS Alternate supply is 72C.

Question 51 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: 31706 User-Defined ID: R51 Cross Reference Number: NEW Topic: Loss of 64C Bus Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following: Major loads powered from electrical buses fed by the emergency generator(s)

ILO EXAM Page: 99 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 51 Table-Item Links Plant Procedures 20.300.64C NUREG 1123 KA Catalog Rev. 2 264000 K3.03 4.1*/4.2* Major loads powered from electrical buses fed by the emergency generator(s)

ILO EXAM Page: 100 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 52 ID: R52 Points: 1.00 The plant is experiencing a loss of air event. Station air header is 73 psig with all Station Air Compressors running.

At this time, air supply to PCMS isolation valves is ____________________________________.

A. provided by Station Air B. provided by Instrument Air C. provided by Non-Interruptible Air D. isolated due to low Interruptible Air System pressure Answer: C Answer Explanation Correct Answer C - Enclosures in 20.129.01 show PCMS is an NIAS load. At this air pressure, all air supplies are isolated except NIAS.

Plausible Distractors:

A - Knowledge misconception - NIAS load B - Knowledge misconception - NIAS load D - Knowledge misconception - NIAS load Question 52 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 3.00 System ID: 31707 User-Defined ID: R52 Cross Reference Number: NEW Topic: Station Air Loss Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following:

Cross-over to other air systems ILO EXAM Page: 101 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 52 Table-Item Links Plant Procedures 20.129.01 23.129 NUREG 1123 KA Catalog Rev. 2 300000 K4.02 3/3 Cross-over to other air systems ILO EXAM Page: 102 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 53 ID: R53 Points: 1.00 The plant is operating at 100% power with all equipment available when alarm 5D9, TBCCW Heat Exch Disch Temp High/Low is received. The following conditions are observed:

P43-R803, TBCCW HX Temperature, indicates 88°F.

P43-K817, TBCCW TCV P43-F402 Ctrlr, is in Auto.

P43-F402 indicates FULL OPEN.

Which of the following actions, if taken, would correct this abnormal TBCCW system condition?

A. Slowly open P4100-F080A(B), TBCCW HX GSW Inlet Valve, and open P4300-F601(F602), TBCCW HX Inlet Iso Valve, for the standby TBCCW Heat Exchanger.

B. Close P4100-F146, GSW Rtrn From TBCCW TCV Restricting Orifice Iso Vlv and throttle P4100-F147, GSW Rtrn From TBCCW Restricting Orifice Bypass Vlv.

C. Verify closed P4300-F601(F602), TBCCW HX Inlet Iso Valve, and slowly open P4100-F080A(B), TBCCW HX GSW Inlet Vlv for the standby TBCCW Heat Exchanger.

D. Place P43-K817 in MANUAL and incrementally adjust TBCCW Outlet Temperature by controlling P43-F402, TBCCW HX Inlet Iso Valve, in manual.

Answer: A Answer Explanation Correct Answer A - SOP direction is to valve in the cooling water (GSW) and then open the inlet isolation valve to place another HX in service.

Distractors:

B - plausible because it appears to apply more cooling water.

C - plausible -- correct valves, but they are not in the correct order of operation.

D - plausible - if the controller had failed in AUTO. There is no indication of this and F402 is currently FO.

ILO EXAM Page: 103 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 3.00 System ID: 32926 User-Defined ID: R53 Cross Reference Number: NEW Topic: Loss of TBCCW Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mc Comments: KA - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: High/low CCW temperature Question 53 Table-Item Links Plant Procedures 23.128 05D009 NUREG 1123 KA Catalog Rev. 2 400000 A2.03 2.9/3 High/low CCW temperature ILO EXAM Page: 104 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 54 ID: R54 Points: 1.00 The plant is at 86% power with rod pattern adjustments in progress when the following indications are received:

3D80, Control Rod Drift, alarms.

No control rod positions indicated on four rod display.

No RED full out or GREEN full in lights lit on full core display.

Based on these indications, what actions are appropriate?

A. Enter 20.106.07, Control Rod Drift.

B. Place the Reactor Mode Switch to SHUTDOWN.

C. Stop any control rod movements in progress, per 20.106.08, RPIS Failure D. Substitute rod positions for control rods with bad indications per 23.608, Rod Worth Minimizer.

Answer: C Answer Explanation Correct Answer C These conditions indicate a total loss of RPIS. The first action is to stop any rod motion in progress.

Plausible Distractors:

A. is incorrect since the drift alarm is due to loss of rod positions for all rods.

B. is incorrect since there is no safety reason to shutdown the reactor at this time.

D. is incorrect since it is a loss of all rod position indication.

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: 3.00 System ID: 31288 User-Defined ID: R54 Cross Reference Number: NEW Topic: Loss of RPIS Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 doug Comments: KA - Ability to monitor automatic operations of the CONTROL ROD AND DRIVE MECHANISM including: Control Rod Position ILO EXAM Page: 105 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 54 Table-Item Links Plant Procedures 20.106.08 NUREG 1123 KA Catalog Rev. 2 201003 A3.01 3.7/3.6 Control rod position ILO EXAM Page: 106 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 55 ID: R55 Points: 1.00 A plant startup is in progress with Reactor Power at 9% when the Feedwater Control System Steam Flow digital output fails downscale.

Which one of the following describes the effect on rod movement?

A. The RWM will enforce rod movement at all power levels.

B. Rod blocks will only be generated at power levels above 12%.

C. The RWM must be bypassed to allow rod movement until power reaches 12%.

D. Rod movement would be prevented by a withdraw error enforced by the RWM.

Answer: A Answer Explanation The RWM will enforce rod movement based on the selected rod sequence up to the low power setpoint (LPSP). LPSP is in effect until feedwater flow is >12.275% and steam flow is >12.25%.

With the steam flow failed low, the LPSP would never be reached.

B is plausible, rod blocks will be enforced at all power levels with a failed steam flow output.

C is plausible, LPSP is enforced until steam flow is >12.25% not power.

D is plausible, WE (withdraw error) would be enforced for incorrectly selected rod below the LPSP.

Question 55 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: 31587 User-Defined ID: R55 Cross Reference Number: NEW Topic: RWM - setpoints Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 6 Text Field: ILO 2013 mike Comments: KA - Knowledge of the effect that a loss or malfunction of the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) will have on following: Reactor manual control system ILO EXAM Page: 107 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 55 Table-Item Links Plant Procedures 23.608 NUREG 1123 KA Catalog Rev. 2 201006 K3.01 3.2/3.5 Reactor manual control system: P-Spec(Not-BWR6)

ILO EXAM Page: 108 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 56 ID: R56 Points: 1.00 During an EECW System surveillance with the plant operating at 100% power, P4400-F606B, EECW Supply to Div 2 EECW Drywell Equipment Isolation valve suddenly closes.

Which of the following describes the impact of this fault and any required operator actions?

A. RR MG Set bearing damage could occur. Trip RR Pump B.

B. RR Pump motor damage could occur. If flow cannot be restored within 2 minutes trip RR Pump B.

C. RR Pump seal damage could occur. If seal cavity temperature exceeds 180°F, Recirc Pump B must be shutdown.

D. RR MG Set North Cooling Fan air temperatures could increase. If MG set air temperature exceeds 260°F, trip RR Pump B.

Answer: B Answer Explanation Without cooling, RR MG set should be tripped within 2 minutes. Motor damage may occur.

A. is plausible, but cooling would still be available to MG set bearings.

C. is plausible, Seal Temperature alarms at 160°F and pump should be tripped and isolated at

>200°F.

D. is plausible, but cooling would still be available to MG set cooling unit.

Question 56 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: 31588 User-Defined ID: R56 Cross Reference Number: 315-0167-B007-005 Topic: EECW Valve Failure Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 4 Text Field: ILO 2013 mike Comments: KA - Knowledge of the operational implications of the following concepts as they apply to RECIRCULATION SYSTEM :

Pump/motor cooling ILO EXAM Page: 109 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 56 Table-Item Links Plant Procedures 20.127.01 23.138.01 03D146 03D161 NUREG 1123 KA Catalog Rev. 2 202001 K5.03 2.7/2.7 Pump/motor cooling: Plant-Specific ILO EXAM Page: 110 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 57 ID: R57 Points: 1.00 The Plant is operating at 100% when 1D66, STEAM LEAK DETECTION AMBIENT TEMP HIGH, alarms.

It is determined that the Reactor Water Cleanup Pump Room A temperature is reading 177°F. The CRNSO observes the P602 panel and notices that G3352-F004, RWCU SUPPLY OTBD ISO VLV, is CLOSED. All other indications are normal.

Given the above conditions, which of the following statements describes ALL of the expected operator responses?

A. Close G3352-F119 RWCU SUPPLY SUCT ISO VLV and G3352-F220 RWCU TO FW OTBD CNTM ISO VLV and trip RWCU pumps.

B. Close G3352-F001 RWCU INBD ISO VLV and G3352-F220 RWCU TO FW OTBD CNTM ISO VLV.

C. Close G3352-F119 RWCU SUPPLY SUCT ISO VLV and G3352-F220 RWCU TO FW OTBD CNTM ISO VLV.

D. Close G3352-F001 RWCU INBD ISO VLV and G3352-F220 RWCU TO FW OTBD CNTM ISO VLV and trip RWCU pumps.

Answer: D Answer Explanation RWCU Area Temperature High >175°F will cause auto closure of G3352-F001,F004,F220 and result in a low flow RWCU pump trip. With temperature reading 177°F all valves should have isolated and pumps should have tripped with the closure of G3352-F004 causing low flow trip.

A. Is plausible, G3352-F119 does not receive an auto closure signal for high room temp B. Is plausible, G3352-F001,F220 will need to be isolated but pump must also be tripped C. Is plausible, G3352-F119 does not receive an auto closure signal for high room temp ILO EXAM Page: 111 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 3.00 System ID: 31606 User-Defined ID: R57 Cross Reference Number: NEW Topic: RWCU valve isolations Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Valve closures Question 57 Table-Item Links Plant Procedures 01D66 23.707 NUREG 1123 KA Catalog Rev. 2 204000 A2.10 2.7/2.8 Valve closures ILO EXAM Page: 112 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 58 ID: R58 Points: 1.00 Control rod operability surveillance is in progress at full power. With Control Rod 22-15 selected at 48, an insert signal is applied, and the following is displayed on the RWM:

SR 22-15 FF Self Test OK Mode OPERATE What do these indications mean to the operator?

A. RPIS digital inputs are not valid at this position.

B. Rod Worth Minimizer has blocked rod movement.

C. RPIS position is a substituted value for this position.

D. RPIS position is bypassed in the Rod Worth Minimizer.

Answer: A Answer Explanation If either digit of the RPIS input position is inoperable, an "FF" will be displayed.

B. Functional misconception - RWM is automatically bypassed. Cannot be true at full power.

C. Functional misconception - If the rod has a substituted position, the position indication will be displayed in blue on IPCS display.

D. Functional misconception - If the rod is bypassed in RWM, its I.D. will be displayed using inverse video on the RWM.

Question 58 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: 31289 User-Defined ID: R58 Cross Reference Number: NEW Topic: RPIS - RWM Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of the physical connections and/or cause-effect relationships between ROD POSITION INFORMATION SYSTEM and the following: RWM ILO EXAM Page: 113 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 58 Table-Item Links Plant Procedures 23.608 NUREG 1123 KA Catalog Rev. 2 214000 K1.01 3/3.2 RWM: Plant-Specific ILO EXAM Page: 114 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 59 ID: R59 Points: 1.00 The plant is operating in Mode 3 with Division 1 RHR in Shutdown Cooling mode when RPV level begins lowering due to unknown reasons. The following indications are observed:

Narrow range RPV level show a 6 difference between instruments Wide range shows a 20 difference between indicators Occasional notching is occurring on all instruments Which of the following operator actions should be taken at this time?

A. Insert all control rods not fully inserted.

B. Verify Main Turbine Bypass Valves are closed.

C. Verify Reference Leg Backfill is in service with proper flow rate.

D. Isolate SDC by closing Shutdown Cooling Suction Isolation Valves E1150-F008 and E1150-F009.

Answer: D Answer Explanation 22.000.02 P&L 3.4.1 states "If level anomalies (level indication deviates more than 5" on narrow range indication, 22" on wide range indication or notching occurs) and an unexplained loss of RPV level occurs, take immediate action to isolate SDC by closing E1150-F008, RHR SDC Otbd Suction Iso Vlv, and E1150-F009, RHR SDC Inbd Suction Iso Vlv, and refer to 20.205.01, "Loss of Shutdown Cooling."

A. plausible if thought is to ensure reactor is fully shut down.

B. plausible if thought is that failed open TBVs are causing RPV level loss.

C. plausible due to malfunction of backfill causing loss of level indications.

Question 59 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: 31726 User-Defined ID: R59 Cross Reference Number: NEW Topic: Startup P & L Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 doug Comments: KA - Ability to manually operate and/or monitor in the control room: Recorders ILO EXAM Page: 115 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 59 Table-Item Links Plant Procedures 22.000.02 NUREG 1123 KA Catalog Rev. 2 216000 A4.01 3.3/3.1 Recorders ILO EXAM Page: 116 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 60 ID: R60 Points: 1.00 The plant has experienced a LOCA. Current plant conditions are as follows:

Drywell pressure 15.7 psig Torus pressure 9.9 psig Drywell Temperature 230°F Torus Temperature 120°F Which system/subsystem would the crew use to lower drywell pressure under these post-LOCA conditions?

A. Torus Hardened Vents B. Drywell Spray C. Torus Spray D. RBHVAC Answer: B Answer Explanation 23.205 System Description describes function of Drywell Spray A. Function misconception; not used for this condition C. Function misconception; does not spray in drywell or lower drywell pressure D. Function misconception; not used for this condition Question 60 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: 31746 User-Defined ID: R60 Cross Reference Number: NEW Topic: RHR Contaiment Spray Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 8 Text Field: ILO 2013 doug/PAT Comments: KA - RHR/LPCI: CMT Spray Mode - Knowledge of system purpose and/or function ILO EXAM Page: 117 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 60 Table-Item Links Plant Procedures 23.205 NUREG 1123 KA Catalog Rev. 2 G2.1.27 3.9/4.0 Knowledge of system purpose and or function 226001 RHR/LPCI: Containment Spray System Mode ILO EXAM Page: 118 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 61 ID: R61 Points: 1.00 The design feature in Extraction Steam and Heater Drains that ensures Turbine isolation from high energy condensate contained in the heater shells and prevents water induction is:

A. Extraction steam is directed from the HP and LP turbines to the Main Condenser.

B. Feedwater heater emergency drain valves open upon a Turbine trip to relieve heater levels and prevent water induction into the turbine.

C. Extraction Steam Motor Operated and Air Operated Inlet Valves to Feedwater Heaters 3, 4, 5, and 6 close upon receipt of a High-High level signal from their respective Heaters.

D. Extraction Steam System Inlet Drain Valves and their respective isolation valves open if either the air operated check valves are closed or the motor operated isolation valves are out of the full open position.

Answer: C Answer Explanation Extraction Steam Motor Operated and Air Operated Inlet Valves to Feedwater Heaters 3, 4, 5, and 6 are interlocked to close upon receipt of a High-High level signal from their respective Heaters. If the Turbine trips, interlocks will also cause the Air Operated Valves to close. These interlocks ensure Turbine isolation from the high energy condensate contained in the heater shells and prevent water induction. As pressure in the Turbine decreases following a turbine trip, this condensate could flash and cause the Turbine to overspeed. Also water from a leaking heater tube is prevented from backing up to the Turbine A. is plausible, but extraction steam is normally directed to the FW heaters.

B. is plausible, but does not prevent water induction.

D. is plausible, but prevents condensate in lines.

Question 61 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: 31747 User-Defined ID: R61 Cross Reference Number: NEW Topic: Main Steam Interlocks Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Knowledge of MAIN AND REHEAT STEAM SYSTEM design feature(s) and/or interlocks which provide for the following: Over pressure control ILO EXAM Page: 119 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 61 Table-Item Links Plant Procedures 23.108 NUREG 1123 KA Catalog Rev. 2 239001 K4.07 3.7/3.7 Over pressure control ILO EXAM Page: 120 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 62 ID: R62 Points: 1.00 A plant startup is in progress. Reactor power is 50%, and the North RFP is feeding the RPV. Low Main Turbine lube oil pressure then causes a Main Turbine Trip.

Ten minutes after the trip, the North Reactor Feed Pump is .

A. running on low pressure steam B. running on high pressure steam C. tripped due to the loss of low pressure steam D. tripped due to the loss of high pressure steam Answer: B Answer Explanation LP Steam from the MSR supplies the RFPT while the turbine is operating at 50% power. RFPT steam supply automatically shifts from low pressure steam to high pressure steam when insufficient LP steam is available. Ten minutes after a Trubine Trip, there is not enough LP pressure steam and the HP steam will take over.

A. is plausible, but after 2 minutes low pressure steam from the MSR is exhausted.

C. is plausible, but the RFPT will switch over to HP steam.

D. is plausible, but the HP steam will continue to operate the RFPT.

Question 62 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: 31306 User-Defined ID: R62 Cross Reference Number: NEW Topic: RFP - MT interelatioship Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 5 Text Field: ILO 2013 doug/pt Comments: KA - Knowledge of the effect that a loss or malfunction of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on following: Reactor Feedwater Pump ILO EXAM Page: 121 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 62 Table-Item Links Plant Procedures 23.107 23.109 20.000.21 NUREG 1123 KA Catalog Rev. 2 245000 K3.05 2.7/2.8 Reactor feedwater pump: Plant-Specific ILO EXAM Page: 122 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 63 ID: R63 Points: 1.00 Plant is operating at 65% power when the the CRNSO notes the following conditions:

6D15, Off Gas Hydrogen High, alarms.

Hydrogen concentration indicates 2.5% on the OG Hydrogen Concentration Recorder.

Local readings at the Hydrogen Analyzer Panel are 2.5% Channel A and 2.4% Channel B.

The in-service recombiner temperature is 635°F and lowering.

Given these conditions, which of the following actions should the crew take?

A. Determine the OG Oxygen Concentration.

B. Commence a plant shutdown to Hot Standby.

C. Place the standby recombiner train in service.

D. Immediately place the Reactor Mode Switch in Shutdown.

Answer: C Answer Explanation 20.712.01 action for hydrogen >1% but <4%.

A. is a possible misconception if a combustible or explosive mixture is a concern.

B. is action for offgas explosion.

D. is not a conservative action Question 63 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: 31748 User-Defined ID: R63 Cross Reference Number: NEW Topic: Off-Gas Hydrogen Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 doug Comments: KA - Ability to predict and/or monitor changes in parameters associated with operating the OFFGAS SYSTEM controls including: Hydrogen gas concentration ILO EXAM Page: 123 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 63 Table-Item Links Plant Procedures 20.712.01 NUREG 1123 KA Catalog Rev. 2 271000 A1.13 3.2/3.7 Hydrogen gas concentration ILO EXAM Page: 124 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 64 ID: R64 Points: 1.00 One day in August, the plant is operating at rated power with GSW Pumps 2, 5 and 6 in service. A loss of 4160v Bus 68K occurs due to a bus lockout. How is fire header pressure maintained in this condition?

A. Fire Jockey Pump continues to run. No other fire pumps start.

B. Electric Fire Pump starts on low pressure. Fire Pump Jockey Pump trips.

C. Diesel Fire Pump starts on low pressure. Fire Pump Jockey Pump continues to run.

D. Diesel Fire Pump starts on low pressure. Fire Pump Jockey Pump trips.

Answer: C Answer Explanation Loss of 68K results in loss of two of the operating GSW pumps, numbers 5 and 6 as well as the Electric Fire Pump (68K). The Fire Pump Jockey pump is supplied by 72K which is powered by 69K. A common misconception is that 72K is powered from 68K not 69K and that this would also be lost on a loss of 68K.

Plausible Distractors:

A The Fire Pump Jockey pump is insufficient to maintain fire header pressure with only one GSW pump running.

B Functional misconception - EFP does not start due to no power available and the Jockey Pump continues to operate D Functional misconception - DFP auto start is required to maintain pressure, but the Fire Pump Jockey Pump does not trip.

Question 64 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: 31749 User-Defined ID: R64 Cross Reference Number: NEW Topic: Fire Protection Pumps Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 doug Comments: KA - Fire Protection: Knowledge of electrical power supplies to the following: Pumps ILO EXAM Page: 125 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 64 Table-Item Links Plant Procedures 23.501.01 20.300.68K NUREG 1123 KA Catalog Rev. 2 286000 K2 02 2.9/3.1 Pumps ILO EXAM Page: 126 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 65 ID: R65 Points: 1.00 The plant has experienced an earthquake. During the transient a jet pump becomes displaced due to a failure of its hold down beam. What is the potential safety concern?

A. APRM high flux setpoints will be non-conservatively affected.

B. Proper core submergence post-LOCA cannot be maintained.

C. Indicated core flow may be lower than actual.

D. Loop jet pump flows cannot be matched.

Answer: B Answer Explanation A displaced Jet Pump could cause a loss of the ability to re-flood the core to at least 2/3 core height (design bases)

A. is incorrect because APRM high flux setpoints are representative of reactor power from the LPRM system, not core flow. It is not affected.

C. is incorrect because indicated core flow may be higher than actual (AOP).

D. is incorrect because the operator will still have the ability to control RRMG speeds and loop flows.

Question 65 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: 31946 User-Defined ID: R65 Cross Reference Number: NEW Topic: Jet Pump Failure Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 3 Text Field: ILO 2013 mc Comments: KA - Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR VESSEL INTERNALS:

Reactor Recirc ILO EXAM Page: 127 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 65 Table-Item Links Plant Procedures 23.605 20.138.02 20.138.02 Bases NUREG 1123 KA Catalog Rev. 2 290002 K6.03 3.1/3.2 Recirculation system ILO EXAM Page: 128 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 66 ID: R66 Points: 1.00 During the mitigation of an Anticipated Transient Without SCRAM (ATWS), the following conditions exist.

RPV Water Level has been intentionally lowered Reactor Power lowered to 2x103 cps on the Source Range Which ONE of the following indications, alone, indicates that the reactor will remain shutdown during a cooldown?

A. Standby Liquid Control Boron Tank Level is 45 inches.

B. 1290 lbs of borax and 1290 lbs of boric acid have been injected.

C. Standby Liquid Control Boron Tank Level is 26 inches.

D. 3300 lbs of Borax and 3300 lbs of Boric Acid have been injected.

Answer: D Answer Explanation Cold shutdown Boron weight assures the Reactor will remain shutdown during a cooldown. 3300 lbs exceeds the 3215 lbs as stated in 29.100.01 Sheet 1A A. is plausible, Hot Shutdown Boron Weight is 45 inches B. is plausible, Hot Shutdown Boron Weight is 1290 lbs of borax and boric acid C. is plausible, Cold shutdown tank level is 16 inches not 26 inches Question 66 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: 35566 User-Defined ID: R66 Cross Reference Number: 802-3003-0118-001 Topic: Cold SD Boron weight Num Field 1: LOK:L Num Field 2: 10 CFR55.41(b)10 Text Field: ILO 2013 Comments: KA-Ability to identify diverse indications to validate the response of another indicator ILO EXAM Page: 129 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 66 Table-Item Links Plant Procedures 29.100.01 SH 1A NUREG 1123 KA Catalog Rev. 2 G2.1.45 4.3/4.3 Ability to identify and interpret diverse indications to validate the response of another indication ILO EXAM Page: 130 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 67 ID: R67 Points: 1.00 The plant is operating at 100% power in a black board condition when the CRNSO notices that the VAS display shows 3D19 as red, the SOER screen display shows the following:

This information indicates that the VAS system will incur (1) of functionality and will result in (2) .

(See attached ARP 3D19.)

A. (1) loss (2) loss of redundancy for one half side of VAS I/O B. (1) no loss (2) loss of P601 through P805 window failures C. (1) no loss (2) loss of redundancy for one half side of VAS I/O D. (1) loss (2) loss of P601 through P805 window failures Answer: D ILO EXAM Page: 131 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Answer Explanation Alarm 3D19, Annunciator System Trouble, indicates a potential problem with the VAS system.

The SOER screen display shows that MUXA/C have been lost. Flow chart in 3D19 indicates loss of VAS functionality and loss of annunciation for P601 through P805.

A this would be correct for a two MUX failure but redundancy would be lost for one side of VAS/IO B this would be correct for a single MUX failure but P601 through P805 would remain functional C this would be correct for a single MUX failure Question 67 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: 31887 User-Defined ID: R67 Cross Reference Number: 26575 Topic: MUX Failures Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 mike Comments: KA - Ability to use plant computers to evaluate system or component status.

Provide copy of 3D19 for MUX failures.

Question 67 Table-Item Links Plant Procedures 03D019 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: 132 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 68 ID: R68 Points: 1.00 How is system configuration control maintained during a Local Leak Rate Test (LLRT)?

A. Test procedure steps are followed to maintain system configuration.

B. Operator Tags (white tag, red lettering) are hung to maintain system configuration.

C. Caution Tags (yellow with black lettering) are hung to maintain system configuration.

D. System Supervisor Tags (red tag, white lettering) are hung to maintain system configuration.

Answer: A Answer Explanation Per MOP 12, Caution Tags should not be used to provide configuration control during activities covered by another procedure (relay testing, LLRT, etc.). The procedure should maintain configuration control by way of procedure steps or special controls.

C. Is plausible but is prohibited by MOP 12 B. Is plausible but is not permitted by MOP 12. Operator tagged equipment shall not be operated under any condition D. Is plausible but is not permitted by MOP 12. System Supervisor's tags shall be used exclusively when ordered by the System Supervisor.

Question 68 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: 31888 User-Defined ID: R68 Cross Reference Number: 638-0101-0101-003 Topic: Configuration control Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 mike Comments: KA - Knowledge of the process for controlling equipment configuration or status ILO EXAM Page: 133 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 68 Table-Item Links Plant Procedures MOP12 - Tagging and Protective Barrier System NUREG 1123 KA Catalog Rev. 2 G2.2.14 3.9/4.3 Knowledge of the process for controlling equipment configuration or status ILO EXAM Page: 134 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 69 ID: R69 Points: 1.00 Which one of the following situations is appropriate for the use of Temporary Change Notice per MGA 04?

A. Change the intent of a system operating procedure section.

B. Change the approval requirement for an administrative procedure.

C. Correct a component identification in a system operating procedure.

D. Add a corrective action to prevent recurrence to an existing procedure.

Answer: C Answer Explanation This is allowed by MGA04.

A is plausible, but intent changes are prohibited by MGA 04.

B is plausible, but temporary changes to administrative procedures is prohibited by MGA 04.

D is plausible, but addition of corrective actions is prohibited by MGA 04.

Question 69 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: 31166 User-Defined ID: R69 Cross Reference Number: 802-4101-0013-008 Topic: Use of Temporary Change Notice Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 Comments: KA - Knowledge of the process for making changes to procedures.

Question 69 Table-Item Links Plant Procedures MGA04 NUREG 1123 KA Catalog Rev. 2 G2.2.6 3.0/3.6 Knowledge of the process for making changes to procedures ILO EXAM Page: 135 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 70 ID: R70 Points: 1.00 When venting Primary Containment, per the EOPs, to maintain Primary Containment Pressure less than the PCPL, which is the preferred vent path to use and why?

A. The Drywell is preferred because the elevation of the Drywell vent is higher than the Torus vent which is generally preferred to minimize ground-level releases.

B. The Drywell is preferred since the lower elevation of the Torus vent may cause it to become submerged and not capable of withstanding vent flow.

C. The Torus is preferred since the Torus Hardened Vent is capable of withstanding the pressure and temperature demands of venting with the plant under DBA conditions.

D. The Torus is preferred to reduce radioactivity released by the scrubbing action of the Torus water.

Answer: D Answer Explanation The torus is the preferred vent path due to the scrubbing action.

A. is plausible, the DW elevation is higher but is not the preferred path.

B. is plausible, Torus vent is at a lower elevation then DW vents C. is plausible, the correct vent path but wrong reason Question 70 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: 35606 User-Defined ID: R70 Cross Reference Number: 802-0004-0109-011 Topic: Venting to maintain PCPL Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 7 Text Field: ILO 2013 Comments: KA - Ability to control radiation releases.

ILO EXAM Page: 136 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 70 Table-Item Links Plant Procedures BWROG EPGs Volume 1 NUREG 1123 KA Catalog Rev. 2 G2.3.11 3.8/4.3 Ability to control radiation releases ILO EXAM Page: 137 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 71 ID: R71 Points: 1.00 You have just left a contaminated area and are required to perform a frisk using a hand-held frisker.

What action is required if the background reading is 340 cpm?

A. Contact Radiation Protection.

B. Perform a whole body frisk at a rate of 2 inches per minute.

C. Perform a whole body frisk at a rate of 0.5 inches per second.

D. Set the hand held frisker to the next highest range.

Answer: A Answer Explanation MRP04, Enclosure B, page 3 of 7, states "Note the background reading on the meter. If 300 cpm or greater, contact Radiation Protection."

B & C are incorrect - a proper whole body frisk takes approximately three minutes to perform.

Training material states that monitoring is performed about one half inch from the frisker probe at a speed of about 2 inches per second.

D is incorrect - the instrument should be on the X1 range and SLOW response.

Question 71 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: 31208 User-Defined ID: R71 Cross Reference Number: 508-0001-0036-001 Topic: Frisk Using a Hand-Held Frisker Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 12 Text Field: ILO 2013 Comments: KA - Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

ILO EXAM Page: 138 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 71 Table-Item Links Plant Procedures MRP 04 NUREG 1123 KA Catalog Rev. 2 G2.3.5 2.9/2.9 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

ILO EXAM Page: 139 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 72 ID: R72 Points: 1.00 You have been assigned to the FIN Team to enter the RHR HX Room to perform a visual inspection. You have reviewed a survey of the room and received a pre-job brief to become knowledgeable of the Routine Specific RWP for this activity. Based on the survey the following radiological conditions are present in the room:

Highest contamination level 750 dpm/100cm2 beta-gamma General area radiation levels 250 mrem/hr You observe the following posted signs when you arrive at the room:

CAUTION - RADIATION AREA CAUTION - CONTAMINATION AREA What actions are required?

A. Enter the area, and perform the visual inspection.

B. STOP. Notify the control point that the Radiation Area ONLY sign is incorrect.

C. STOP. Notify the control point that the Contamination Area ONLY sign is incorrect.

D. STOP. Notify the control point that the Radiation Area and the Contamination Area signs are BOTH incorrect.

Answer: B Answer Explanation B. The Contamination area sign is correct. The Radiation Sign should be be High Radiation Area based on the general radiation levels.

A. is incorrect because the examinee must know when an area is posted incorrectly.

C. is incorrect because only the radiation area sign is wrong. Plausible because the signs are posted and the examinee must know the levels to get the right selection.

D. is incorrect because only the radiation area sign is wrong. Plausible because the signs are posted and the examinee must know the levels to get the right selection.

ILO EXAM Page: 140 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - 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: 3 Difficulty: 4.00 System ID: 32846 User-Defined ID: R72 Cross Reference Number: NEW Topic: RWP Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 12 Text Field: ILO 2013 mc Comments: KA - Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Question 72 Table-Item Links Plant Procedures MRP 04 NUREG 1123 KA Catalog Rev. 2 G2.3.7 3.5/3.6 Ability to comply with radiation work permit requirements during normal and abnormal conditions ILO EXAM Page: 141 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 73 ID: R73 Points: 1.00 In accordance with MOP10, "Fire Brigade", which one of the following individuals could be assigned to the fire brigade with the plant operating in Mode 1, assuming each individual has met the physical and training requirements?

A. Reactor Operator assigned as Safe Shutdown B. Radwaste Operator assigned as Shift Communicator C. Senior Reactor Operator assigned as the Shift Manager D. Nuclear Operator assigned as Turbine Building Rounds Answer: D Answer Explanation An NO assigned as rounds operator meets the requirements for fire brigade member.

A, B, & C are incorrect - MOP10, sect.3.1.1, does not allow crew members necessary for safe shutdown of the unit, and does not allow the Shift Manager to be a member.

Question 73 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: 31067 User-Defined ID: R73 Cross Reference Number: 802-4101-0028-006 Topic: Fire Brigade Membership Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 Comments: KA - Knowledge of fire protection procedures.

Question 73 Table-Item Links Plant Procedures MOP10 NUREG 1123 KA Catalog Rev. 2 G2.4.25 3.3/3.7 Knowledge of fire protection procedures ILO EXAM Page: 142 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 74 ID: R74 Points: 1.00 What do the following EOP flowchart symbols indicate?

1. 2.

A. 1) Instructional step

2) Hold/Wait step B. 1) Instructional Step

2) Before step C. 1) Decision step

2) Hold/Wait step D. 1) Decision step

2) Before step Answer: D Answer Explanation Diamond shape indicates a Decision Step while the Pentagon represents the Before Step A/B/C are plausible: octagonal shape is a hold/wait point, rectangular shape is an instructional step.

Question 74 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: 31149 User-Defined ID: R74 Cross Reference Number: NEW Topic: EOP Flowchart Symbols Num Field 1: LOK L Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 Comments: KA - Knowledge of general guidelines for EOP usage.

ILO EXAM Page: 143 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 74 Table-Item Links Plant Procedures Fermi Writers Guide App F: EOP Flowcharts NUREG 1123 KA Catalog Rev. 2 G2.4.14 3.8/4.5 Knowledge of general guidelines for EOP usage ILO EXAM Page: 144 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO 75 ID: R75 Points: 1.00 A plant transient occurred, and 29.100.01 Sheets 1A, 2 and 3 were entered. Conditions have continued to deteriorate, and the SAGs are being implemented. Subsequently, an unisolable HPCI steam line rupture occurs.

Based on these conditions, the CRS would continue in the SAGs as directed by the TSC, and

______________________________________________.

A. NOT enter any EOPs B. enter 29.100.01 Sheet 5, Secondary Containment and Rad Release C. enter 29.100.01 Sheet 5, Secondary Containment and Rad Release, and continue in the existing EOPs D. enter 29.100.01 Sheet 5, Secondary Containment and Rad Release, and re-enter 29.100.01 Sheet 1A, RPV Control - ATWS Answer: A Answer Explanation Concerning actions after entry into the SAGs, BWROG EPGs/SAGs, Appendix B states "Additional EOP entry conditions may then be disregarded until the PSAMGs are exited." (page B-4-4)

B, C & D are plausible if the examinee believes we are still operating in the EOPs.

Question 75 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to Complete: 6 Difficulty: 4.00 System ID: 31148 User-Defined ID: R75 Cross Reference Number: NEW Topic: Prioritize EOP/SAG Actions Num Field 1: LOK H Num Field 2: 10 CFR 55.41(b) 10 Text Field: ILO 2013 Comments: KA - Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

ILO EXAM Page: 145 of 146 27 August 2013

EXAMINATION ANSWER KEY 2013 ILO NRC - RO Question 75 Table-Item Links Plant Procedures BWROG EPG App B NUREG 1123 KA Catalog Rev. 2 G2.4.16 3.5/4.4 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as operating procedures, abnormal operating procedures, and severe accident management guidelines ILO EXAM Page: 146 of 146 27 August 2013

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