ML21187A307

Draft Written Examination (Folder 2)

ML21187A307
Person / Time
Site:	Calvert Cliffs
Issue date:	06/16/2021
From:	Thomas Setzer Operations Branch I
To:	Exelon Generation Co
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ML20261H327	List: ML21187A307 ML21187A308 ML21187A309 ML21187A310 ML21189A288 ML21193A298 ML21193A307 ML21193A312 ML21193A316 ML21193A321 ML21193A369 ML21202A164 ML22073A117
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EPID L-2021-OLL-0028
Download: ML21187A307 (226)

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Exam Material VISION Report (Test Key) 2021 ILT NRC RO EXAM CCNPP Operations NRC Examinations February 04, 2021 Test 2021 ILT NRC RO EXAM VISION ID 340926 Status

NISP-TR-01 Form 7 Revision 3 Page 1 of 1 EXAMINATION COVER SHEET Exam Title (ID) 2021 ILT NRC RO EXAM (340926)

Training Program CCNPP Operations NRC Examinations LMS Component ID Total Points 75.00 Pass Criteria = 80 %

Trainee Name Employee ID Graded By / Date Grade ____ / 75.00 = _______ %

Review and Approval Instructor Date Technical Review Date Training Supv Date Examination Rules

1. References may NOT be used during this exam, unless otherwise stated.

2. Read each question carefully before answering. If you have any questions or need clarification during the exam, contact the exam proctor.

3. Conversation with other trainees during the exam is prohibited.

4. Partial credit will NOT be considered, unless otherwise stated. Show all work and state all assumptions when partial credit may be given.

5. Restroom trips are limited and only one examinee at a time may leave.

6. For exams with time limits, you have ____ minutes to complete the exam.

7. The examinee agrees to refrain from discussing the content of the exam until the end of the exam cycle.

Examination Integrity Statement Cheating or compromising the exam will result in disciplinary actions up to and including termination.

I acknowledge that I am aware of the Exam Rules stated above. Further, I have not given, received, or observed any aid or information regarding this exam prior to or during its administration that could compromise this exam.

Examinee Signature ___________________________________________ Date ______________

Review Acknowledgement I acknowledge that the correct answers to the exam questions were indicated to me following the completion of the exam. I have had the opportunity to review the exam questions with the instructor to ensure my understanding.

Examinee Signature ___________________________________________ Date ______________

Exam Material 2021 ILT NRC RO EXAM Test Key Question 1 ID: 2160946 Points: 1.00 Unit-1 is raising reactor power:

The HI POWER TRIP RESET DEMAND alarm is received at 62% power The crew does NOT reset the VOPT setpoint and continues to raise reactor power Which of the following will result from this condition?

A. VOPT will be disabled as reactor power is raised.

B. A Reactor and Main Turbine trip will occur at 64 to 65% power.

C. A Reactor and Main Turbine trip will occur at 70 to 71% power.

D. The alarm will automatically reset the VOPT setpoint 10% higher.

Answer B Answer Explanation A. Incorrect. Plausible is the operator misinterprets this power trip to be like the SUR trip which is only active at lower powers.

B. Correct. Per 1C05-ALM, the trip setpoint is 2.6% higher than alarm setpoint. 62%

plus 2.6% is 64.6%, which is bounded by 64 to 65%.

C. Incorrect. Plausible if the operator misinterprets the trip setpoint is 8.4% higher than the alarm setpoint for the reset but this is the setpoint of the trip from current power level.

D. Incorrect. Plausible if the operator misinterprets the circuitry of the VOPT trip and determines that the setpoint will automatically reset.

Test ID: 340926 02/04/2021 3 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic High Power Trip Reset Demand alarm & do not reset VOPT setpoint; power increase results User ID Q2160946 System ID 2160946 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1C05 Alarm Manual, Window D-08, Rev 04101 Training Objective From memory, recall the Automatic RPS trips, setpoints, indications, and any associated interlocks, in accordance with the 1C05 Alarm Manual.

Previous NRC Exam Use None K/A Reference(s)

EPE.007.EA2.06 Safety Function 1 Tier 1 Group 1 RO Imp: 4.3 SRO Imp: 4.5 Ability to determine or interpret the following as they apply to a reactor trip: (CFR 41.7 / 45.5 / 45.6)

Occurrence of a reactor trip Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links Table: TRAINING-QUESTION-AN-OPS-Safety Functions 14 - Procedures Test ID: 340926 02/04/2021 4 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 2 ID: 2152056 Points: 1.00 Unit-1 is operating at 100% power:

An RCS overpressure condition occurs The reactor trips A Pressurizer Safety Valve opens during the transient and fails to reseat Which of the following describes:

(1) The minimum pressure the RCS reached for the Pressurizer Safety Valve to open?

And, (2) The impact on Pressurizer level indication with the valve stuck open?

A. (1) 2400 PSIA (2) Pressurizer level indication is lowering B. (1) 2400 PSIA (2) Pressurizer level indication is rising C. (1) 2500 PSIA (2) Pressurizer level indication is lowering D. (1) 2500 PSIA (2) Pressurizer level indication is rising Answer D Answer Explanation A. Incorrect. (1) Plausible if the candidate misinterprets the setpoint for the PORVs with the setpoint for the Safety Valves. (2) Plausible if the candidate misinterprets that since the safety valve is relieving RCS water to the quench tank that the level in the PZR will be lowering.

B. Incorrect. (1) See above. (2) Correct.

C. Incorrect. (1) Correct. (2) See above.

D. Correct. (1) Per USFAR Table 4-19, the first PZR Safety Valve will lift at 2500 PSIA.

(2) Per EOP-5-TB, level will be rising due to the lowering of pressure in the PZR Test ID: 340926 02/04/2021 5 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key causing a swell type effect.

Question Information Topic Setpoint of PZR safety valve and impact on PZR level User ID Q2152056 System ID 2152056 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.3 Mechanical components and design features of the reactor 10CFR55 Content primary system.

References Provided None K/A Justification The understanding of the mismatch between a lowering of actual RCS inventory and a rising PZR level indication is tested.

SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # UFSAR, Rev 49, Table 4-19 1C06-ALM, Rev 53 EOP-5-TB, Rev 03300 Training Objective State the operating characteristics of the PZR code safety valves.

Previous NRC Exam Use None K/A Reference(s)

APE.008.AK2.02 Safety Function 3 Tier 1 Group 1 RO Imp: 2.7* SRO Imp: 2.7 Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: (CFR 41.7 / 45.7)

Sensors and detectors Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 6 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 3 ID: 2160947 Points: 1.00 (1) Which of the following is the basis for maintaining an upper subcooling limit margin of 140°F during EOP-5?

And, (2) What action must be taken if subcooling exceeds 140°F?

A. (1) Prevents a pressurized thermal shock event occurrence (2) Increase steaming rate and maximize HPSI injection B. (1) Ensures an adequate volume of subcooled liquid is available for decay heat removal (2) Increase steaming rate and maximize HPSI injection C. (1) Ensures an adequate volume of subcooled liquid is available for decay heat removal (2) Secure Pressurizer Heaters D. (1) Prevents a pressurized thermal shock event occurrence (2) Secure Pressurizer Heaters Answer D Answer Explanation A. Incorrect - (1) Correct as stated below. (2) Incorrect since increasing steaming rate and maximizing HPSI injection would raise subcooling. Plausible since these actions are contained in EOP-5 Block Step K for controlling subcooling.

B. Incorrect - (1) Incorrect but plausible since this is the EOP-5 basis for maintaining Pressurizer Level, not for maintaining subcooled margin < 140°F. The volume of subcooled fluid does not have a direct correlation to the degree of subcooling. (2)

Incorrect as stated above.

C. Incorrect - (1) Incorrect as stated above. (2) Incorrect as stated below.

D. Correct - (1) As stated in the Caution of EOP-5 Block Step K: The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization. (2) As stated in the EOP-5 Basis Document and Block Step K, securing Pressurizer Heaters will lower RCS pressure, lowering subcooling.

Test ID: 340926 02/04/2021 7 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic EOP-5 Upper Subcooled Margin Basis/Corrective measures User ID Q2160947 System ID 2160947 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # EOP-5 Rev 03001 EOP-5 Basis Document Rev 03300 Training Objective Knowledge of the reasons for the following responses as they apply to the Small Break LOCA: Maintenance of RCS Subcooling.

Previous NRC Exam Use NRC RO Exam - 12/2008 K/A Reference(s)

P2.4.20 Safety Function 3 Tier 3 Group RO Imp: 3.8 SRO Imp: 4.3 Knowledge of the operational implications of EOP warnings, cautions, and notes.

(CFR: 41.10 / 43.5 / 45.13)

GE.4.0.EPE.009 Safety Function 3 Tier 1 Group 1 RO Imp: SRO Imp:

Small Break LOCA Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 8 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 4 ID: 2155342 Points: 1.00 Unit 2 is operating at 100% power:

A loss of Component Cooling Water to 21A Reactor Coolant Pump occurs Which one of the following statements correctly describes:

(1) The temperature limit (lowest temperature) for RCP controlled Bleedoff that requires a reactor trip?

And, (2) The reason for the limit?

A. (1) 200°F controlled bleedoff temperature (2) To prevent damage to the RCP seals B. (1) 200°F controlled bleedoff temperature (2) To prevent damage to the thrust bearing C. (1) 250°F controlled bleedoff temperature (2) To prevent damage to the RCP seals D. (1) 250°F controlled bleedoff temperature (2) To prevent damage to the thrust bearing Answer A Answer Explanation A. Correct. (1) Per OI-1A, the trip criteria for CBO is 200 degrees. (2) Per OI-1A, operating the RCPs with CBO temperature above 200 degrees could result in complete seal failure.

B. Incorrect. (1) Correct. (2) See below.

C. Incorrect. (1) See below. (2) Correct.

D. Incorrect. (1) Plausible if the candidate misinterprets that 250 degrees is both the temperature limit for CBO requiring the seals to be rebuilt and the trip criteria. (2)

Plausible if the candidate misinterprets the reason for main turbine trip temperature criteria as the same for the RCPs.

Test ID: 340926 02/04/2021 9 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Recall the limits for and basis for the limits on bleedoff temperature.

User ID Q2155342 System ID 2155342 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-7C Training Objective Specify the limits for and basis for the limits on bleedoff temperature.

Previous NRC Exam Use 2006 NRC RO K/A Reference(s)

APE.015/017.AK2.07 Safety Function 4 Tier 1 Group 1 RO Imp: 2.9 SRO Imp: 2.9 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: (CFR 41.7 / 45.7)

RCP seals Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 10 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 5 ID: 2161267 Points: 1.00 Unit-1 is operating with the following initial conditions:

The plant was shut down 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago following an extended full power run Shutdown Cooling is in service using 11 LPSI pump RCS temperature is 180°F and slowly lowering RCS pressure is 120 PSIA with a bubble in the Pressurizer Both S/Gs are available A total loss of all Component Cooling Water flow occurs.

Which one of the following is the FIRST action required to establish an RCS Heat Sink?

A. Allow RCS to heat up, then control RCS temperature by bleeding steam from Steam Generators and use AFW to maintain levels.

B. Verify RCS pressure is less than 210 PSIA and align a Containment Spray pump for shutdown cooling.

C. Maintain 11 LPSI Pump in service and open the PORVs to provide core cooling.

D. Start a HPSI Pump and open the PORVs to provide core cooling.

Answer A Answer Explanation A. Correct-With total loss of CCW flow, AOP-7C directs the implementation of AOP-3B in parallel when on SDC. Loss of CCW affects SDC as a common mode failure (no CCW to the SDC HXs.) Per AOP-3B, if the RCS can be pressurized, then Section VI is implemented first to utilize the SGs as the heat removal path.

B. Incorrect-Plausible since CS Pumps do not require CCW for cooling and this is a heat removal path in AOP-3B. Loss of CCW, however, affects the SDC HXs.

C. Incorrect-Plausible since this is heat removal path in AOP-3B, but only if SGs were not available.

D. Incorrect-Plausible since this is heat removal path in AOP-3B, but only if SGs were not available.

Test ID: 340926 02/04/2021 11 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic First actions upon loss of SDC (AOP-3B) based on plant conditions User ID Q2161267 System ID 2161267 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # AOP-3B-1 Rev 03100 Training Objective Respond to a loss of SDC with pressurization of the RCS possible per AOP-3B.

Previous NRC Exam Use NRC RO Exam - 12/2008 K/A Reference(s)

APE.025.AK1.01 Safety Function 4 Tier 1 Group 1 RO Imp: 3.9 SRO Imp: 4.3 Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat Removal System: (CFR 41.8 / 41.10 / 45.3)

Loss of RHRS during all modes of operation Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 12 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 6 ID: 2155362 Points: 1.00 Unit 1 is operating at 100% power the following alarm is received:

(1) What is the impact on the plant?

And (2) What action should be taken per the alarm manual to mitigate this impact?

A. (1) Reactor power rises (2) Verify 11 and 12 CC Heat Exchanger Temperature Control Bypass valves are open.

B. (1) Reactor power rises (2) Verify Ion Exchangers bypass valve in bypass.

C. (1) Reactor power lowers (2) Verify 11 and 12 CC Heat Exchanger Temperature Control Bypass valves are open.

D. (1) Reactor power lowers (2) Verify Ion Exchangers bypass valve in bypass.

Answer D Answer Explanation A. Incorrect - (1) Incorrect but plausible if the impact of high CC temperature on letdown temperature and boron on the IX is misinterpreted as causing power to rise. Power would not rise in this case since boron in the CVCS IX would be released from the resin causing RCS boron concentration to rise and reactor power to lower. (2) Incorrect but plausible since the alarm manual says to verify the positions of the Bypass valves but to verify these valves are shut.

B. Incorrect - (1) Incorrect but plausible if the impact of high CC temperature on letdown temperature and boron on the IX is misinterpreted as causing power to rise. (2) Correct Test ID: 340926 02/04/2021 13 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key as stated below.

C. Incorrect - (1) Correct as stated below. (2) Incorrect but plausible since the alarm manual says to verify these valves are shut.

D. Correct - (1) Correct per 1C13, this alarm will cause letdown temperatures to increase causing power to lower. (2) Correct since the alarm manual action is to ensure the Ion Exchangers bypass valve opens to protect the resin from high temperatures.

Question Information Topic Impact of high CCW temperature on the plant User ID Q2155362 System ID 2155362 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided Embedded Reference K/A Justification No additional information SRO-Only Justification N/A Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-7C, Rev 5 1C13, Rev 55 Training Objective Given a scenario and/or plant parameters, determine the required actions in accordance with AOP-7C.

Previous NRC Exam Use None K/A Reference(s)

APE.026.AA1.02 Safety Function 8 Tier 1 Group 1 RO Imp: 3.2 SRO Imp: 3.3 Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: (CFR 41.7 /

45.5 / 45.6)

Loads on the CCWS in the control room Test ID: 340926 02/04/2021 14 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 15 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 7 ID: 2161271 Points: 1.00 Unit-1 is at 100% with the following initial conditions:

Pressurizer Pressure Controller PIC-100X is the selected Control Channel and is in AUTO Pressurizer Spray Valve Controller HIC-100 is in Auto RCS Pressure is 2250 PSIA Which one of the following is the IMMEDIATE plant response if the setpoint of PIC-100X, Pressurizer Pressure Controller, fails to 1500 PSIA?

A. Pressurizer Spray Valve Controller HIC-100 output goes to maximum; Proportional heaters output goes to maximum amps.

B. Pressurizer Spray Valve Controller HIC-100 output goes to minimum; Proportional heaters output goes to minimum amps.

C. Pressurizer Spray Valve Controller HIC-100 output goes to minimum; Proportional heaters output goes to maximum amps.

D. Pressurizer Spray Valve Controller HIC-100 output goes to maximum; Proportional heaters output goes to minimum amps.

Answer D Answer Explanation A. Incorrect - The first part is correct as stated below. The second part is incorrect: The Proportional heater output would go to minimal as well due to the mismatch. Heater output going to maximum is plausible if the operator believes the Proportional Heaters act like the Backup heaters and the Proportional Heaters will also energize on an insurge. The insurge would be created by maximum spray collapsing the Pressurizer bubble causing Pressurizer level to rise. Also plausible if the operator misinterprets the operation of the output signal to be the same direction as the Spray Valve controller.

B. Incorrect - The first part is incorrect: The Spray Valve controller going to minimal output is plausible if the Operator believes the Spray Valve controller output will go in the same direction as the Proportional Heater output. When the setpoint of PIC-100X fails low, this will cause the Spray Valve controller to go to maximum output as the actual RCS pressure of 2250 will be above setpoint of 1500. The second part is correct as stated below.

Test ID: 340926 02/04/2021 16 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key C. Incorrect - The first part is incorrect as stated above. The second part is incorrect as stated above.

D. Correct - The first part is correct: When the setpoint of PIC-100X fails low, it causes a mismatch with the indicating pressure (process variable) being higher than the setpoint.

The controller will automatically adjust its output to lower pressure to the new setpoint.

This Spray Valve controller to go to maximum output to provide maximum Main Spray flow as the actual RCS pressure of 2250 psia will be above setpoint of 1500 psia. The second part is correct: The Proportional heater output would go to minimal as well to also lower actual pressure due to the mismatch.

Question Information Topic Selected PZR pressure controller setpoint fails to 1500 PSIA User ID Q2161271 System ID 2161271 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1C06 Alarm Manual, Rev 05300 Training Objective Given a failure of any RCS pressure, temperature or level instrument, predict the response on the system (heaters, main spray, charging, and letdown) to that failure.

Previous NRC Exam Use NRC RO Exam - 6/2016 K/A Reference(s)

APE.027.AK2.03 Safety Function 3 Tier 1 Group 1 RO Imp: 2.6 SRO Imp: 2.8 Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: (CFR 41.7 / 45.7)

Controllers and positioners Test ID: 340926 02/04/2021 17 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 18 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 8 ID: 2155363 Points: 1.00 Which ONE of the following Nuclear Instrument (NI) indications would require actions for an ATWS?

A. LRNI power is 10% and SUR is 1.5 DPM.

B. VOPT was reset at 65% and NI power is 70%.

C. WRNI power is 2x10-3 % and SUR is 3.0 DPM.

D. VOPT was reset at 10% and NI power is 20%.

Answer C Answer Explanation A. Incorrect. Plausible since the SUR trip is active at this power level and the operator misinterprets the SUR pre-trip as the trip setpoint. 1.5 DPM exceeds the pre-trip setpoint but not the trip setpoint of 2.43 DPM.

B. Incorrect. Plausible if the candidate misinterprets when the high power reset alarm will come in (5-6%) vice when RPS will actually trip the reactor (8.4%)

C. Correct. Per 1C05-ALM, A reactor trip will occur at 2.43 DPM when power is between 10-5% and 14%.

D. Incorrect. Plausible since power is 10% greater than the last reset which would normally cause a trip but VOPT is not active at this power level.

Question Information Topic ATWS conditions based on NI readings - #2 User ID Q2155363 System ID 2155363 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.6 Design, components, and functions of reactivity control 10CFR55 Content mechanisms and instrumentation.

References Provided None Test ID: 340926 02/04/2021 19 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Modified Difficulty 2 Technical Reference and Revision # TS 3.3.1, Amend 326 1C05-ALM, Rev 04101 Training Objective Recognize the conditions which would constitute an Anticipated Transient Without Scram (ATWS).

Previous NRC Exam Use 2018 NRC RO K/A Reference(s)

EPE.029.EA2.01 Safety Function 1 Tier 1 Group 1 RO Imp: 4.4 SRO Imp: 4.7 Ability to determine or interpret the following as they apply to an ATWS: (CFR 43.5 / 45.13)

Reactor nuclear instrumentation Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links Table: TRAINING-QUESTION-AN-OPS-Safety Functions 01 - Reactivity Control Test ID: 340926 02/04/2021 20 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 9 ID: 2161278 Points: 1.00 Upon completion of the EOP-0 Safety Function assessments, the crew provides the following reports:

Reactivity Control is complete; no alternate actions taken Turbine Trip is complete; no alternate actions taken Vital Auxiliaries is complete; no alternate actions taken Pressure and Inventory Control cannot be met due to low PZR pressure and level; alternate actions taken Core and RCS Heat Removal is complete; no alternate actions taken Containment Environment is complete; no alternate actions taken Radiation Levels External to Containment cannot be met due to high radiation levels on the WRNGM, Condenser Off-Gas, and S/G Blowdown; alternate actions taken Which one of the following is the correct EOP the crew will implement?

A. EOP-4 B. EOP-5 C. EOP-6 D. EOP-8 Answer C Answer Explanation A. Incorrect - Plausible since an ESDE would cause low PZR pressure and level and the Pressure and Inventory Control safety function to be not met requiring alternate actions.

B. Incorrect - Plausible since a LOCA would cause low PZR pressure and level and the Pressure and Inventory Control safety function to be not met requiring alternate actions.

Also, a LOCA will often cause a rising indication on the Wide Range Noble Gas Monitor and the Radiation Levels External to Containment safety function to be not met.

C. Correct - According to EOP-0, the listed safety functions that are not met and the alternate actions performed for the reasons listed all match the criteria for EOP-6 entry due to a Steam Generator Tube Rupture.

Test ID: 340926 02/04/2021 21 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key D. Incorrect - Plausible since the operator may misinterpret the reports provided to match those of more than one event in progress and will then conclude that EOP-8 will be implemented.

Question Information Topic EOP-6 entry criteria and indications User ID Q2161278 System ID 2161278 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty Technical Reference and Revision # EOP-0-1, Rev 01300 Training Objective Identify the indications of a Steam Generator Tube Rupture and how to differentiate from a LOCA or ESDE.

Previous NRC Exam Use None K/A Reference(s)

P2.4.4 Safety Function 1 Tier 3 Group RO Imp: 4.5 SRO Imp: 4.7 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.10 / 43.2 / 45.6)

GE.4.0.EPE.038 Safety Function 3 Tier 1 Group 1 RO Imp: SRO Imp:

Steam Generator Tube Rupture (SGTR)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 22 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 10 ID: 2152508 Points: 1.00 EOP-7, Station Blackout, has maximum steady state battery discharge rates for the 4 DC buses.

Which of the following describes:

(1) The action required when these steady state amp limits are exceeded?

And, (2) The basis for this action?

A. (1) Shed loads from the affected DC Bus (2) Ensure battery capacity is maintained B. (1) Shed loads from the affected DC Bus (2) Protect non-vital instrumentation from damage C. (1) Secure the affected DC Bus (2) Ensure battery capacity is maintained D. (1) Secure the affected DC Bus (2) Protect non-vital instrumentation from damage Answer A Answer Explanation A. Correct. (1) Per EOP-7, when steady state amps are above the limits, load shedding will be required. (2) Per EOP-7-TB, the maximum amp levels are to ensure battery discharge rates to ensure battery capacity of greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

B. Incorrect. (1) Correct. (2) See below.

C. Incorrect. (1) See below. (2) Correct.

D. Incorrect. (1) Plausible since this is the action if battery volts are below the required limits and the candidate misinterprets the actions for volt limits vice amp limits. (2)

Plausible if the candidate misinterprets that buses with high amp readings will cause damage to instruments since buses with volts outside the limits can cause damage.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Station Blackout - battery discharge rates vs capacity User ID Q2152508 System ID 2152508 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-7-2, Rev 02102 EOP-7 TB, Rev 02302 From memory, describe the operations and design Training Objective features of the following major components, in accordance with Plant Operating Procedures: 125 VDC Batteries.

Previous NRC Exam Use None K/A Reference(s)

EPE.055.EK1.01 Safety Function 6 Tier 1 Group 1 RO Imp: 3.3 SRO Imp: 3.7 Knowledge of the operational implications of the following concepts as they apply to the Station Blackout: (CFR 41.8

/ 41.10 / 45.3)

Effect of battery discharge rates on capacity Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 24 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 11 ID: 2162519 Points: 1.00 Unit-2 is operating at 100% power A steam line break occurs outside of containment SIAS actuation occurs 3 minutes later:

A loss of offsite power occurs Both safety related buses are powered from the EDGs With no operator action, which of the following describes the status of the following pumps:

(1) Are the HPSI pumps running?

And, (2) Are the CS pumps running?

A. (1) Yes (2) Yes B. (1) Yes (2) No C. (1) No (2) No D. (1) No (2) Yes Answer A Answer Explanation A. Correct. (1) Per LD-58, both HPSI pumps are on the LOCI sequencer which will start after a SIAS and UV. (2) Per LD-58, both CS pumps are on the LOCI sequencer which will start after a SIAS and UV.

B. Incorrect. (1) Correct. (2) See below.

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Exam Material 2021 ILT NRC RO EXAM Test Key C. Incorrect. (1) Plausible if the candidate misinterprets the operation of the LOCI sequencer and concludes that the HPSI pumps will have to be manually started after the EDG picks up the bus like the charging pumps. (2) Plausible if the candidate recalls that a Containment Spray actuation signal is not received and misinterprets that the CS pumps will not receive a start signal since containment pressure is normal with the steam line break outside of containment.

D. Incorrect. (1) See above. (2) Correct.

Question Information Topic LOCI Sequencer loads User ID Q2162519 System ID 2162519 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-2, Rev 01700 61058ASH0001, Rev 0055 Training Objective Given a set of plant conditions, demonstrate an understanding of the entry conditions, strategy, major actions and bases of EOP-2, AOP-3E or AOP-3F, as applicable.

Previous NRC Exam Use None K/A Reference(s)

APE.056.AA1.06 Safety Function 6 Tier 1 Group 1 RO Imp: 3.6* SRO Imp: 3.6*

Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power: (CFR 41.7 / 45.5 / 45.6)

Safety injection pump Test ID: 340926 02/04/2021 26 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 27 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 12 ID: 2152525 Points: 1.00 Unit-1 is operating at 100% power:

An electrical transient occurs The Reactor is tripped EOP-0, Post Trip Immediate Actions, is implemented Which of the following describes:

(1) What is the minimum number of 120V AC Vital Buses that have to be energized to call Vital Auxiliaries complete?

And, (2) The reason for why these many buses are required?

A. (1) 3 (2) Ensure power is provided to plant computer and data acquisition systems.

B. (1) 3 (2) Ensure the 2 out of 4 logic for ESFAS actuations is not met C. (1) 4 (2) Ensure power is provided to plant computer and data acquisition systems D. (1) 4 (2) Ensure the 2 out of 4 logic for ESFAS actuations is not met Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

B. Correct. (1) Per EOP-0, 3 120VAC buses is required. (2) Per EOP-0-TB, 3 buses ensure there are not unneeded ESFAS actuations.

C. Incorrect. (1) Plausible if the candidate misinterprets that the number of required 125V DC buses is the same as for 120V AC buses. (2) Plausible if the candidate misinterprets the bases for the other non-vital 120V buses.

D. Incorrect. (1) See above. (2) Correct.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic EOP-00 actions for loss of vital AC Bus User ID Q2152525 System ID 2152525 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 2 Technical Reference and Revision # EOP-0-1, Rev 01400 EOP-0-TB, Rev 02200 Training Objective Monitor and operate the 125 VDC, 120 VAC, and instrument AC Systems per the Calvert Cliffs operating license and approved plant procedures during Normal, Abnormal and Emergency conditions.

Previous NRC Exam Use None K/A Reference(s)

APE.057.AK3.01 Safety Function 6 Tier 1 Group 1 RO Imp: 4.1 SRO Imp: 4.4 Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: (CFR 41.5,41.10 / 45.6 / 45.13)

Actions contained in EOP for loss of vital ac electrical instrument bus Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 29 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 13 ID: 2161414 Points: 1.00 Given the following:

Both Units are operating at 100% power when a Station Blackout occurs 125 VDC Bus voltages are approaching 105 VDC Which, if any, DG combinations, when restored, will ultimately restore a Battery Charger to 11, 12, 21 and 22 125 VDC Buses?

A. 1A; 2A B. 1B; 2B C. 2A; 2B D. None of the listed combinations will restore a Battery Charger to each 125VDC Bus.

Answer C Answer Explanation A. Incorrect - The 1A & 2A DGs power only the Battery Chargers associated with 11 and 22 125 VDC Buses. Plausible if the candidate misinterprets the power supplies to the Battery Chargers and concludes that any Unit 1 and any Unit 2 EDG is required.

B. Incorrect - The 1B & 2B DGs power only the Battery Chargers associated with 12 and 21 125 VDC Buses. Plausible if the candidate misinterprets the power supplies to the Battery Chargers and concludes that any Unit 1 and any Unit 2 EDG is required.

C. Correct - The 2A & 2B DGs power one Battery Charger associated with each of the four 125 VDC Buses.

D. Incorrect - The 2A & 2B DGs power one Battery Charger associated with each of the four 125 VDC Buses. Plausible if the candidate misinterprets the power supplies to the Battery Chargers and concludes that at least 3 EDGs or at least an A Train EDG from one Unit along with a B Train EDG from the other Unit are required to supply all battery chargers.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Relationship of EDGs and 125 VDC User ID Q2161414 System ID 2161414 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.8 Components, capacity, and functions of emergency systems.

References Provided None K/A Justification No additional K/A justification information SRO-Only Justification N/A Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-7J-1, Rev 24 AOP-7J-2, Rev 19 EOP-7-1, Rev 21 EOP-7-2, Rev 20 Training Objective Evaluate the relationships and physical connections between the 120VDC distribution systems and the 480V AC systems.

Previous NRC Exam Use NRC RO Exam - August 2010 K/A Reference(s)

APE.058.AA1.03 Safety Function 6 Tier 1 Group 1 RO Imp: 3.1 SRO Imp: 3.3 Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7 / 45.5 / 45.6)

Vital and battery bus components Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 31 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 14 ID: 2155562 Points: 1.00 Unit 1 is at 100% power:

The following alarms are received:

11 SRW Head Tank Level 12 SRW Head Tank Level 12 SRW HDR Pressure Low The Reactor Operator determines the leak is on 12 SRW Header.

Which of the following components could be the source of the leak on 12 SRW Header?

A. 11 SFP Heat Exchanger B. 12 SFP Heat Exchanger C. 12 S/G Blowdown Heat Exchanger D. 22 S/G Blowdown Heat Exchanger Answer A Answer Explanation A. Correct. Per AOP-7B, 12 header cools 11 SFP Heat Exchanger.

B. Incorrect. Plausible if the candidate recalls the normal numbering scheme of 12 components on 12 header and misinterprets that this is the case for SFP also.

C. Incorrect. Plausible if the candidate recalls the normal numbering scheme of 12 components on 12 header and misinterprets that this is the case for S/G Blowdown also.

D. Incorrect. Plausible if the candidate misinterprets that even components are cooled by the even numbered header as is the case for most of the plant equipment.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Location of a leak in the SRW system User ID Q2155562 System ID 2155562 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # 1C13-ALM, Rev 05600 AOP-7B-1, Rev 1306 Training Objective Given plant conditions, diagnose a Loss of Service Water and respond by directing and/or implementing the proper operator actions in accordance with the following procedures.

Previous NRC Exam Use None K/A Reference(s)

APE.062.AA2.01 Safety Function 4 Tier 1 Group 1 RO Imp: 2.9 SRO Imp: 3.5 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: (CFR: 43.5 /

45.13)

Location of a leak in the SWS Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 33 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 15 ID: 2161415 Points: 1.00 U-1 is operating at 100% power when the following transient occurs:

Instrument Air pressure is lowering and is currently 72 PSIG Plant Air pressure is lowering and is currently 88 PSIG Both Saltwater Air Compressors are manually started Which of the following lists ALL additional automatic system responses that should have occurred?

Condition 1 - PA to IA Cross Connect, 1-PA-2061-CV, opened Condition 2 - Standby Plant Air Compressor started Condition 3 - CNTMT IA SUPPLY, 1-IA-2085-CV, shut A. Conditions 1 and 2 ONLY B. Conditions 1 and 3 ONLY C. Conditions 2 and 3 ONLY D. Conditions 1, 2, AND 3 Answer D Answer Explanation A. Incorrect. Conditions 1 and 2 are correct as stated below. Incorrect since the distractor does not include Condition 3. Not including Condition 3 is plausible if the candidate misinterprets the circuit logic to shut IA supply CV and concludes it is the same as the IA supply MOV to Containment which shuts on a CIS actuation.

B. Incorrect. Conditions 1 and 3 are correct as stated below. Incorrect since the distractor does not include Condition 2. Not including Condition 2 is plausible since each unit has its own Plant Air system and will conclude that an air leak on Unit-1 will not start the PAC on Unit-2. However, there is a cross tie between the units on the PA system. Per AOP-7D, standby PAC will start at a PA pressure of 91 PSIG.

C. Incorrect. Conditions 2 and 3 are correct as stated below. Incorrect since the distractor does not include Condition 1 but plausible if the candidate misinterprets the setpoint of the PA to IA Cross Connect and concludes the automatic action to open has not occurred yet.

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Exam Material 2021 ILT NRC RO EXAM Test Key D. Correct. Condition 1 is correct: Per AOP-7D, this will automatically happen as PA-2061-CV will open when IA pressure reaches 88 PSIG. Condition 2 is correct: Per AOP-7D, this will automatically happen as standby PAC will start at a PA pressure of 91 PSIG. Condition 3 is correct: Per AOP-7D, this will automatically happen as IA-2085-CV will shut at an IA pressure of 75 PSIG.

Question Information Topic Lowering IA Pressure Response User ID Q2161415 System ID 2161415 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Modified Difficulty Technical Reference and Revision # AOP-7D-1 Training Objective Identify the design features that provide a backup for the instrument air system during a partial or total loss of the system.

Previous NRC Exam Use NRC RO Exam - 8/2018 K/A Reference(s)

GE.4.0.APE.065 Safety Function 8 Tier 1 Group 1 RO Imp: SRO Imp:

Loss of Instrument Air P2.2.44 Safety Function 8 Tier 3 Group RO Imp: 4.2 SRO Imp: 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12)

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Exam Material 2021 ILT NRC RO EXAM Test Key Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 36 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 16 ID: 2155602 Points: 1.00 Unit-2 is operating at 100% power:

• Main Generator has a reactive load of 200 MVARs in the LAG direction

• Main Generator Voltage Regulator is in MANUAL The TSO requests raising switchyard 500 Kv voltage by 10 Kv Which ONE of the following is a concern when raising the switchyard voltage by 10 Kv?

A. There will be an increase in grid frequency B. There will be an increase in generator heating C. There will be a decrease in 13 KV Bus Voltage D. There will be a decrease in 120V Vital AC Bus Voltage Answer B Answer Explanation A. Incorrect. Increase in grid frequency is plausible if candidate misinterprets real and reactive loads. Raising switchyard voltage will not change grid frequency as frequency is controlled by true loads on the grid . Raising voltage will just change the reactive load on the Generator.

B. Correct - Increasing the excitation to raise switchyard voltage will also increase MVARs and the apparent power of the Generator (higher reactive and the same true power.) This will result in increased generator heating .

C. Incorrect - Plausible if the candidate misinterprets the impact of the voltage regulator in manual as being the same as the load tap changers being in manual. As 500 Kv Bus voltage is raised , all downstream busses will increase (13Kv, 4Kv, and 480V) on both units.

D. Incorrect - 120V Vital AC voltage rising is plausible if candidate believes all downstream busses will change when switchyard voltage is increased. However, 120V Vital AC bus voltage will be unaffected since Vital AC is derived from inverters off the 125VDC batteries. This system would not be affected by an increased switchyard voltage.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Consequences of an overexcited Main Generator User ID Q2155602 System ID 2155602 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-7M, Rev 00300 OI-43A, Rev 04000 Training Objective Given an anticipated or actual grid disturbance, determine and implement the correct actions to mitigate the event in accordance with plant operating procedures.

Previous NRC Exam Use None K/A Reference(s)

APE.077.AK1.02 Safety Function 6 Tier 1 Group 1 RO Imp: 3.3 SRO Imp: 3.4 Knowledge of the operational implications of the following concepts as they apply to Generator Voltage and Electric Grid Disturbances:

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

Over-excitation Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 38 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 17 ID: 2161416 Points: 1.00 A main steam line break has occurred on Unit-1 and SIAS has actuated. The appropriate EOP directs throttling HPSI flow to maintain pressurizer level, when applicable.

Which one of the following is the basis for maintaining a lower pressurizer level band during the SG blowdown phase as compared to after blowdown is complete?

A. Lower pressurizer level allows for coolant expansion due to heat up after blowdown is complete.

B. Lower pressurizer level allows for RCS subcooling to be maintained low in the band.

C. Lower pressurizer level ensures the pressurizer heaters stay de-energized, minimizing thermal shock.

D. Lower pressurizer level ensures letdown flow will remain at a minimum, reducing the mass loss from the RCS.

Answer A Answer Explanation A. Correct per the EOP-4 basis document step L.3. While the blowdown of the affected S/G is in progress the upper limit on pressurizer level is established at 120 {190} inches.

This lower than normal band for pressurizer level was selected to prevent the pressurizer from going solid due to the RCS heatup and expansion of water after the blowdown phase is completed. This band was chosen based on simulator tests and validation. Simulator exercises have shown that the pressurizer level during larger ESDEs remains below the visible indication until the blowdown is almost complete. This and the fact that small ESDEs allow for less rigorous pressurizer level control will allow for adequate operator control of the pressurizer level during the blowdown phase.

B. Incorrect but plausible since maintaining RCS subcooling low in the band is the strategy and direction provided in EOP-5 and EOP-6.

C. Incorrect but plausible since minimizing thermal shock is a concern used in EOPs when a chance of repressurization exists after a rapid cooldown.

D. Incorrect but plausible since operation of letdown is used in the AOPs and EOPs when pressurizer level has lowered due to a rapid cooldown or a LOCA condition.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic ESDE: why maintain lower PZR level band during blowdown than after blowdown complete User ID Q2161416 System ID 2161416 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # EOP-4-1 EOP-4 Technical Basis Training Objective Determine the correct actions to mitigate the event and evaluate the need for HPSI throttling.

Previous NRC Exam Use None K/A Reference(s) 4.4.E05.EK3.3 Safety Function 4 Tier 1 Group 1 RO Imp: 3.8 SRO Imp: 4.0 Knowledge of the reasons for the following responses as they apply to the (Excess Steam Demand) (CFR: 41.5 /

41.10, 45.6, 45.13)

Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 40 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 18 ID: 2155622 Points: 1.00 Which one of the following is the reason for tripping all reactor coolant pumps per the appropriate optimal EOP when a total loss of all feedwater occurs?

A. Reduces RCP motor damage from steam when once-through core cooling is initiated.

B. Prevents RCP cavitation when the RCS reaches saturation conditions.

C. Delays RCP seal damage when CIS actuates.

D. Reduces heat input to the RCS.

Answer D Answer Explanation A. Incorrect. Plausible since once-through core cooling (OTCC) will cause a steam environment in the containment which could possibly damage the RCPs, but this is not the reason why RCPs are tripped early in EOP-3.

B. Incorrect. Plausible since the RCS will eventually reach saturation conditions after the initiation of OTCC which would damage the RCPs, but this is not the reason why RCPs are tripped early in EOP-3.

C. Incorrect. Plausible since CIS will occur on the initiation of OTCC and will cut off the supply of CCW to the RCPs but this is not the reason why RCPs are tripped early in EOP-3.

D. Correct. Per EOP-3-TB, RCPs are tripped to minimize heat input into the RCS.

Question Information Topic EOP-3: Reason for tripping all RCPs.

User ID Q2155622 System ID 2155622 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

Test ID: 340926 02/04/2021 41 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # EOP-3-TB, Rev 02800 Training Objective Given a loss of all feedwater, identify and understand the basis and take appropriate actions per plant operating procedures to mitigate the event.

Previous NRC Exam Use None K/A Reference(s) 4.4.E06.EK3.2 Safety Function 4 Tier 1 Group 1 RO Imp: 3.2 SRO Imp: 3.7 Knowledge of the reasons for the following responses as they apply to the (Loss of Feedwater) (CFR: 41.5 / 41.10, 45.6 / 45.13)

Normal, abnormal and emergency operating procedures associated with (Loss of Feedwater).

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 42 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 19 ID: 2161417 Points: 1.00 Given the following:

Unit 1 trips from 100% due to a turbine trip Abnormal conditions noted in EOP-0 are two stuck CEAs and 11 Charging Pump tripped EOP-1 is implemented Then the following:

A loss of 14 4KV Bus occurs What is the required action?

A. Implement EOP-8 due to not meeting reactivity control.

B. Implement EOP-2 for the loss of power.

C. Continue with EOP-1 and implement AOP-7I for the loss of power.

D. Implement EOP-8 due to not meeting Vital Auxiliaries.

Answer C Answer Explanation A. Incorrect - The required alternate action of EOP-0 is to establish RCS boration with at least one Charging Pump. When 11 Charging Pump trips, the crew will ensure RCS boration is in progress with 12 or 13 Charging Pump and verify Reactivity Control is met. Plausible if the candidate evaluates the combination of losing 11 Charging Pump and the 14 4KV Bus as causing the inability to use all 3 Charging Pumps and will conclude that RCS Boration is not in progress and reactivity control is no longer met.

B. Incorrect - Incorrect but plausible since EOP-2 deals with the Loss of Offsite Power as well as the Loss of the RCPs and the use of natural circulation. But the RCPs remain in service, so EOP-2 is not required.

C. Correct - Per OP-CA-103-102-1001, Strategies For Successful Transient Mitigation guidance on parallel actions allows the use of AOP-7I to address the loss of 14 4KV Bus.

D. Incorrect - Incorrect but plausible if the candidate misinterprets the EOP-1 safety Test ID: 340926 02/04/2021 43 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key function status checks for the loss of the 14 4KV bus and concludes that Vital Auxiliaries is no longer met. VA is met because only one 4KV bus is required, EOP-8 is not required.

Question Information Topic EOP-1, borating due to 2 stuck CEAs User ID Q2161417 System ID 2161417 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # OP-CA-103-102-1001 Strategies for Successful Transient Mitigation Training Objective Determine required actions for more than one CEAs that fails to fully insert into the core on a reactor trip.

Previous NRC Exam Use NRC RO Exam - 12/2008 K/A Reference(s)

APE.005.AA2.03 Safety Function 1 Tier 1 Group 2 RO Imp: 3.5 SRO Imp: 4.4 Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod: (CFR: 43.5 /

45.13)

Required actions if more than one rod is stuck or inoperable Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 44 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 20 ID: 2156337 Points: 1.00 Unit-1 is operating at 100% power:

1-LT-110X, the process variable on the controlling PZR Level controller fails high Actual Pressurizer Pressure begins to rise Which of the following describes:

(1) The reason why Pressurizer Pressure is rising?

And, (2) Where flashing is prevented by the backpressure regulators response?

A. (1) Backup Heaters energize (2) in the regenerative heat exchanger B. (1) Backup Heaters energize (2) between the flow control valves and the letdown heat exchanger C. (1) Charging flow exceeds letdown flow (2) in the regenerative heat exchanger D. (1) Charging flow exceeds letdown flow (2) between the flow control valves and the letdown heat exchanger Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

B. Correct. (1) Per 1C06, a high level condition will cause all the backup heaters to energize which will cause actual pressurizer pressure to rise. (2) Per USFAR Chapter 9, the "flashing of the hot liquid between the letdown control valves and the letdown heat exchanger is prevented by controlling back pressure with a pressure control valve downstream of the letdown heat exchanger.

C. Incorrect. (1) Plausible if the candidate misinterprets how the PV failing impacts the backup charging pumps and determines all the backup charging pumps start. (2)

Plausible if the candidate misinterprets the location of the backpressure regulators with the flow control valves and determines that the regulators can only protect components Test ID: 340926 02/04/2021 45 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key upstream of them.

D. Incorrect. (1) See above. (2) Correct.

Question Information Topic Pressurizer level control failure impact on pressure and reason User ID Q2156337 System ID 2156337 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # UFSAR, Chapter 9.1, Rev 49 1C06-ALM, Rev 05300 Training Objective Given a set of plant conditions, describe impact on CVCS, and any required operator actions in accordance with the Alarm Manuals, including: Pressure/Level Transmitter failures.

Previous NRC Exam Use None K/A Reference(s)

APE.028.AK3.02 Safety Function 2 Tier 1 Group 2 RO Imp: 2.9 SRO Imp: 3.2 Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions:

(CFR 41.5,41.10 / 45.6 / 45.13)

Relationships between PZR pressure increase and reactor makeup/letdown imbalance Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 46 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 21 ID: 2161435 Points: 1.00 Unit-1 is currently in a refueling outage with fuel movement in the Spent Fuel Pool and Reactor in progress.

A Fuel Handling Incident occurs in Containment and Operations implements AOP-6D, Fuel Handling Incident.

In accordance with AOP-6D, all available IODINE FILT FANS are started AND start times logged.

(1) Why are the Iodine Filter Fans started?

And, (2) What is the minimum number of IRUs required for 100% removal capacity?

A. (1) Reduce potential Iodine concentrations and fission product particulates due to the fuel handling incident.

(2) Two Iodine Filter Units.

B. (1) Reduce potential iodine concentrations due to the fuel handling incident.

(2) One Iodine Filter Unit.

C. (1) Reduce potential iodine concentrations due to the fuel handling incident.

(2) Two Iodine Filter Units.

D. (1) Reduce potential Iodine concentrations and fission product particulates due to the fuel handling incident.

(2) One Iodine Filter Unit.

Answer C Answer Explanation A. Incorrect. (1) Incorrect. Reducing potential iodine concentrations is correct but the IRU will not remove fission product particulates. Plausible if the candidate recalls the IRUs are considered a filtered fan and would conclude that a filter will remove particulates. (2) Correct as stated below.

B. Incorrect. (1) Correct as stated below. (2) Incorrect but plausible since the candidate will recall that only one safety related train is the minimum required to meet design basis accidents.

C. Correct. (1) Correct per AOP-6D which states the IRUs are started to reduce Test ID: 340926 02/04/2021 47 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key potential iodine concentrations. (2) Correct. Each IRU provides 50% capacity, so 2 IRUs will provide 100% required capacity.

D. Incorrect. (1) Incorrect as stated above. (2) Incorrect as stated above.

Question Information Topic Why are Iodine Filter Units started & how many required for 100% cleanup User ID Q2161435 System ID 2161435 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.8 Components, capacity, and functions of emergency systems.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 4 Technical Reference and Revision # AOP-6D AOP-6D Technical Basis Training Objective Determine the required number of IRUs and the function provided during a Fuel Handling Incident.

Previous NRC Exam Use None K/A Reference(s)

APE.036.AK1.01 Safety Function 8 Tier 1 Group 2 RO Imp: 3.5 SRO Imp: 4.1 Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Incidents : CFR 41.8 / 41.10 / 45.3)

Radiation exposure hazards Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 48 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 22 ID: 2155782 Points: 1.00 Unit-2 is operating at 7% power:

The turbine is being rolled for a start up The condenser develops a small vacuum leak Condenser vacuum is 26.7 inches of Hg. and slowly lowering The crew enters AOP-7G, LOSS OF CONDENSER VACUUM Which of the following correctly describes:

(1) The vacuum setpoint at which the Turbine Bypass Valves become unavailable?

And, (2) What does the TBVs becoming unavailable due to lower vacuum protect against?

A. (1) 20 inches Hg (2) Low pressure turbine blades from stationary diaphragm rubbing B. (1) 20 inches Hg (2) Main condenser from overpressure C. (1) 22.5 inches Hg (2) Main condenser from overpressure D. (1) 22.5 inches Hg (2) Low pressure turbine blades from stationary diaphragm rubbing Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

B. Correct. (1) Per AOP-7G, the TBVs become unavailable at 20". (2) Per the AOP basis the reason for the TBV setpoint is to protect the main condenser from overpressure.

C. Incorrect. (1) See below. (2) Correct.

D. Incorrect. (1) Plausible if the candidate misinterprets the Unit 1 and Unit 2 vacuum setpoints for the TBVs. (2) Plausible since the LP turbine blades are sensitive to back Test ID: 340926 02/04/2021 49 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key pressure and stationary diaphragm rubbing, or the candidate misinterprets the reason for the main turbine trip on low vacuum with the reason the TBVs stop working on low vacuum.

Question Information Topic Loss of condenser vacuum impact on TBVs User ID Q2155782 System ID 2155782 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Modified Difficulty 2 Technical Reference and Revision # AOP-7G, Rev 00601 AOP-7G-TB, Rev 00600 Training Objective Identify three major plant components that are affected by a loss of condenser vacuum, and how they impact plant operation.

Previous NRC Exam Use 2011 RO - St Lucie K/A Reference(s)

APE.051.AK3.01 Safety Function 4 Tier 1 Group 2 RO Imp: 2.8* SRO Imp: 3.1*

Knowledge of the reasons for the following responses as they apply to the Loss of Condenser Vacuum: (CFR 41.5,41.10 / 45.6 / 45.13)

Loss of steam dump capability upon loss of condenser vacuum Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 50 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 23 ID: 2161436 Points: 1.00 Using the reference shown (Liquid Waste Discharge Permit):

Both Unit-1 and Unit-2 are operating at 100% power 21A Waterbox removed from service for cleaning A discharge of 12 RCWMT is in progress per the attached permit.

Which one of the following would require termination of the release per CY-CA-170-601?

A. Loss of 12 Circulating Water Pump B. Loss of 23 Circulating Water Pump C. 0-RE-2201 indicates 5.350E+04 cpm D. Release flow rate lowers from 120 GPM to 100 GPM Test ID: 340926 02/04/2021 51 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Answer B Answer Explanation A. Incorrect - The permit only takes credit for Unit-2 CWPs for dilution flowrate.

Plausible if the candidate misinterprets the release flow path according to the permit and concludes that a loss of 12 Circulating Water Pump causes the dilution flowrate to become less than required.

B. Correct - The loss of 23 Circulating Water Pump causes the dilution flowrate to become less than the 5 CW Pumps required by the permit.

C. Incorrect - Plausible since the 0-RE-2201 provided is higher than the RMS Background and higher than the Expected RMS Reading listed on the permit. But the RMS indication has not reached the adjustable setpoint that would cause a termination of the release.

D. Incorrect - Plausible if the candidate misinterprets the meaning of the release flow rate of 120 gpm listed on the permit as being no longer met and then incorrectly concludes that the release will be terminated. But the release flowrate listed on the permit is only a maximum.

Question Information Topic Liquid Radioactive Waste Release Permit User ID Q2161436 System ID 2161436 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided Embedded Reference K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # CY-CA-170-601, Rev 0 OI-17C-4, Rev 01200 Test ID: 340926 02/04/2021 52 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Training Objective Identify operations that require a Gaseous Waste discharge permit.

Previous NRC Exam Use None K/A Reference(s)

APE.059.AA2.02 Safety Function 9 Tier 1 Group 2 RO Imp: 2.9 SRO Imp: 3.9 Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: (CFR: 43.5

/ 45.13)

The permit for liquid radioactive-waste release Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 53 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 24 ID: 2155784 Points: 1.00 Unit-1 is operating at 100% power:

A fire occurred in the Cable Spreading Room The fire is extinguished, but the room remains filled with smoke The smoke removal system is being placed in service per OI-22F, Control Room and Cable Spreading Rooms Ventilation The ABO unlocks and opens the roof hatch door and inlet manual damper Which of the following correctly describes:

(1) Where the controls for the smoke removal system are located?

And, (2) What is the impact on the operability of the Control Room Ventilation when the smoke removal system is placed in operation?

A. (1) Control Room (2) Operable B. (1) Control Room (2) NOT Operable C. (1) 45' Turbine Building (2) NOT Operable D. (1) 45' Turbine Building (2) Operable Answer C Answer Explanation A. Incorrect. (1) Plausible if the candidate misinterprets that the controls for the smoke removal system are in the control room where all the other control room ventilation controls are. (2) Plausible if the candidate misinterprets how the smoke removal system is placed in service for removing smoke from the CSR and determines the control room envelope is not breached.

B. Incorrect. (1) See above. (2) Correct.

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Exam Material 2021 ILT NRC RO EXAM Test Key C. Correct. (1) Per OI-22F, the controls for the smoke removal system are on 1C108 which is on the 45' of the turbine building. (2) Per OI-22F, placing the smoke removal system in operation renders the control room ventilation system inoperable.

D. Incorrect. (1) Correct. (2) See above.

Question Information Topic Operation of the smoke removal system and its impact User ID Q2155784 System ID 2155784 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # OI-22F, Rev 03000 Training Objective Given plant conditions, determine the appropriate actions per TS and procedures for the following systems: Control Room Ventilation.

Previous NRC Exam Use None K/A Reference(s)

APE.067.AA1.05 Safety Function 8 Tier 1 Group 2 RO Imp: 3.0 SRO Imp: 3.1 Ability to operate and / or monitor the following as they apply to the Plant Fire on Site: (CFR 41.7 / 45.5 / 45.6)

Plant and control room ventilation systems Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 55 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 25 ID: 2161439 Points: 1.00 Which one of the following valves is credited to ensure containment integrity per STP-O-55, Containment Integrity Verification?

A. 2-SRW-1582-CV, 21 CAC EMER DISCH in Mode 1 B. 2-PS-5464-CV, RCS SAMPLE ISOL in Mode 5 C. 2-EAD-5463-MOV, CNTMT NORM SUMP DRN in Mode 6 D. 2-SI-4144-MOV, CNTMT SUMP OUTLET ISOL in Mode 3 Answer D Answer Explanation A. Incorrect - Plausible if the candidate recalls that this is a normally shut valve that establishes a SRW flowpath to Containment when opened. Containment Cooler SRW isolation valves receive an ESFAS signal on a SIAS actuation. As long as the valves are operable, containment integrity is maintained. Containment Integrity is verified in Modes 1-4.

B. Incorrect - Plausible if the candidate recalls that this is a normally shut valve that establishes an RCS sample point flowpath from Containment when opened. RCS Sample Isolation valve receives an ESFAS signal on a SIAS actuation to close. As long as the valve is operable, containment integrity is maintained. Containment Closure is verified in Modes 5-6.

C. Incorrect - Plausible if the candidate recalls that this is a normally shut valve that establishes a flowpath from the Containment normal sump when opened. The normal containment sump valves get an ESFAS signal which will automatically shut the valves, so containment integrity is maintained. Containment Closure is verified in Modes 5-6.

D. Correct - Per STP-O-55-2, Att. 2, 2-SI-4144-MOV must be shut. This is a normally shut valve that establishes a flowpath from the Containment emergency sump when opened. Containment Integrity is verified in Modes 1-4.

Test ID: 340926 02/04/2021 56 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Loss of Containment Integrity User ID Q2161439 System ID 2161439 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 4 Technical Reference and Revision # STP O-55-2 Training Objective Evaluate the provided conditions for a Loss of Containment Integrity.

Previous NRC Exam Use NRC RO Exam - 8/2014 K/A Reference(s)

APE.069.AA1.01 Safety Function 5 Tier 1 Group 2 RO Imp: 3.5 SRO Imp: 3.7 Ability to operate and / or monitor the following as they apply to the Loss of Containment Integrity: (CFR 41.7 / 45.5 /

45.6)

Isolation valves, dampers, and electropneumatic devices.

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 57 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 26 ID: 2155822 Points: 1.00 Which of the following completes the statement:

The CVCS Process Radiation Monitor (RI-202) monitors ___(1)___ radiation to detect increases in specific isotopes due to ___(2)___.

A. (1) alpha (2) RCS leaks B. (1) alpha (2) fuel failures C. (1) gamma (2) RCS leaks D. (1) gamma (2) fuel failures Answer D Answer Explanation A. Incorrect. (1) Plausible if the candidate misinterprets that alpha radiation is also released during events and that this is what this monitor measures. (2) Plausible if the candidate misinterprets what this radiation monitor detects and assumed it is used like many of the other ones in the plant which monitor for RCS leaks (COG, BD, WRNGM).

B. Incorrect. (1) See above. (2) Correct.

C. Incorrect. (1) Correct. (2) See above.

D. Correct. (1) Per USFAR chapter 9.1.3.1, the process radiation monitor measures gamma. (2) Per USFAR chapter 9.1.3.1, it is designed to detect activity release from the fuel to the RCS.

Test ID: 340926 02/04/2021 58 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Function of the CVCS process radiation monitor User ID Q2155822 System ID 2155822 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.11 Purpose and operation of radiation monitoring systems, 10CFR55 Content including alarms and survey equipment.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # USFAR Chapter 9.1, Rev 49 1C07-ALM, Rev 03708 Training Objective From memory, state the purpose and functions of the CVCS and its components.

Previous NRC Exam Use None K/A Reference(s)

APE.076.AK2.01 Safety Function 9 Tier 1 Group 2 RO Imp: 2.6 SRO Imp: 3.0 Knowledge of the interrelations between the High Reactor Coolant Activity and the following: (CFR 41.7 / 45.7)

Process radiation monitors Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 59 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 27 ID: 2161446 Points: 1.00 A Small Break Loss of Coolant Accident has occurred.

Which one of the following describes:

(1) The operational implications if natural circulation is established instead of maintaining forced circulation.

And, (2) The consequences if reflux boiling is established as the heat removal method.

A. (1) Main PZR spray will not be available (2) SGs are no longer effective at removing any heat B. (1) Main PZR spray will not be available (2) RCS inventory will be below the top of the hot leg C. (1) Allowable cooldown rate is lower, increasing time until SDC can be established (2) SGs are no longer effective at removing any heat D. (1) Allowable cooldown rate is lower, increasing time until SDC can be established (2) RCS inventory will be below the top of the hot leg Answer B Answer Explanation A. Incorrect:

(1) Correct. Per EOP-5, Loss of Coolant Accident, with no RCPs in operation, Main PZR spray is not available.

(2) Incorrect. S/Gs not available as a heat sink is plausible to the Operator if they believe boiling in the core is the only heat transfer mechanism occurring during reflux boiling. During reflux boiling, RCS level will be below the top of the hot leg to allow the reflux process to occur. Steam leaving the core is condensed in the SG U-Tubes and that condensate than travels back to the core via the hot leg to repeat the heat removal process.

B. Correct:

(1) Correct. Per EOP-5, with no RCPs in operation, Main PZR spray is not available.

(2) Correct. During reflux boiling, RCS level will be below the top of the hot leg to allow the reflux process to occur. Steam leaving the core is condensed in the SG U-Tubes Test ID: 340926 02/04/2021 60 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key and that condensate than travels back to the core via the hot leg to repeat the heat removal process.

C. Incorrect:

(1) Incorrect. A lower cooldown rate is plausible to the Operator since EOP-6, Steam Generator Tube Rupture, cooldown rate limits are lower when on natural circulation (35F/hr when on natural circulation.) During a natural circulation cooldown in EOP-5, the allowable cooldown rate is the same for both natural and forced circulation

(<100F/hr.)

(2) Incorrect. S/Gs not available as a heat sink is plausible to the Operator if they believe boiling in the core is the only heat transfer mechanism occurring during reflux boiling. During reflux boiling, RCS level will be below the top of the hot leg to allow the reflux process to occur. Steam leaving the core is condensed in the SG U-Tubes and that condensate than travels back to the core via the hot leg to repeat the heat removal process.

D. Incorrect:

(1) Incorrect. A lower cooldown rate is plausible to the Operator since EOP-6 cooldown rate limits are lower when on natural circulation (35F/hr when on natural circulation.)

During a natural circulation cooldown in EOP-5, the allowable cooldown rate is the same for both natural and forced circulation (<100F/hr.)

(2) Correct. During reflux boiling, RCS level will be below the top of the hot leg to allow the reflux process to occur. Steam leaving the core is condensed in the SG U-Tubes and that condensate than travels back to the core via the hot leg to repeat the heat removal process.

Question Information Topic Natural Circ and Reflux implications during a SBLOCA User ID Q2161446 System ID 2161446 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.2 General design features of the core, including core structure, 10CFR55 Content fuel elements, control rods, core instrumentation, and coolant flow.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Test ID: 340926 02/04/2021 61 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Type Bank Difficulty Technical Reference and Revision # EOP-5-1 EOP-5 Technical Basis Training Objective Identify the core heat removal mechanisms for a large or small break LOCA.

Previous NRC Exam Use NRC RO Exam - 6/2016 K/A Reference(s)

GE.4.4.A16 Safety Function 2 Tier 1 Group 2 RO Imp: SRO Imp:

Excess RCS Leakage P2.4.9 Safety Function 2 Tier 3 Group RO Imp: 3.8 SRO Imp: 4.2 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 62 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 28 ID: 2155983 Points: 1.00 Unit-1 is operating at 100% power:

The 11A RCP Seal Temperature Hi-Press alarm occurs The following are the readings for the 11A RCP Upper Seal Pressure Middle Seal Pressure Which of the following describes which seal is failed for 11A RCP?

A. Lower Seal B. Middle Seal C. Upper Seal D. Vapor Seal Answer C Answer Explanation Test ID: 340926 02/04/2021 63 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key A. Incorrect. Plausible if the candidate misinterprets the guidance which states that the pressure values will point away from the failure, and incorrectly thinks the values will point towards the failed seal.

B. Incorrect. Plausible if the candidate misinterprets that since the middle seal is reading half of RCS pressure that it is the failed seal since the lower and upper must be breaking down the other 1150 pounds of pressure.

C. Correct. Per OI-1A, on an upper seal failure the upper pressure goes to ~50 and the middle seal is ~1150.

D. Incorrect. Plausible if the candidate misinterprets that since upper seal pressure is at the pressure the vapor seal normally sees that the vapor seal is failed.

Question Information Topic Diagnosis an upper seal failure on 11A RCP User ID Q2155983 System ID 2155983 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.3 Mechanical components and design features of the reactor 10CFR55 Content primary system.

References Provided Embedded Reference K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # OI-1A, Rev 04400 Training Objective Given a set of RCP seal indications, determine the status of the seal.

Previous NRC Exam Use None K/A Reference(s)

SF4.003.A4.05 Safety Function 4 Tier 2 Group 1 RO Imp: 3.1 SRO Imp: 3.0 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)

RCP seal leakage detection instrumentation Test ID: 340926 02/04/2021 64 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 65 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 29 ID: 2161128 Points: 1.00 Reactor power is currently stable at 88%. Current Burnup is 10,000 MWD/MTU.

A malfunction occurs, causing the Letdown HX CCW Temperature Control valve to close.

Which one of the following identifies the initial response of reactor power and TCOLD to this failure?

A. Reactor power rises, TCOLD lowers.

B. Reactor power rises, TCOLD rises.

C. Reactor power lowers, TCOLD lowers.

D. Reactor power lowers, TCOLD rises.

Answer C Answer Explanation A. Incorrect. Plausible if candidate misinterprets the effect of the temperature change and incorrectly concludes that the RCS temperature will be lowered by a lowered Letdown temperature causing reactor power to rise and Tcold to lower. It is incorrect since the effect of the temperature change is on the CVCS IXs causing boron concentration to lower and reactor power to rise.

B. Incorrect. Plausible if candidate misinterprets that since the valve is reverse acting the temperature will lower causing boron concentration to lower and power and Tcold will rise.

C. Correct. TIC-223, failing to 100%, causes CCW flow to be secured to the L/D Hx. Per OI-16, As L/D temperature rises the CVCS Ion Exchangers slough boron. The rise in Boron concentration will cause Reactor power to lower, lowering TCOLD.

D. Incorrect. Plausible if the candidate misinterprets the impact of a change in Boron on Tcold and determines that Tcold will rise as Boron levels change. Also, plausible if candidate misinterprets the effect of the temperature change and incorrectly concludes that the RCS temperature will be raised by a higher Letdown temperature causing reactor power to lower and Tcold to rise.

Test ID: 340926 02/04/2021 66 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Explain the effects of increasing/decreasing Letdown temperature.

User ID Q2161128 System ID 2161128 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 4 Technical Reference and Revision # OI-16, Rev 04100 Training Objective Analyze the effects of changes (rise/lower) in Letdown temperature when flowing thru IXs.

Previous NRC Exam Use 2008 NRC RO K/A Reference(s)

SF1.004.K3.06 Safety Function 1 Tier 2 Group 1 RO Imp: 3.4 SRO Imp: 3.6 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: (CFR: 41.7/45/6)

RCS temperature and pressure Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 67 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 30 ID: 2155924 Points: 1.00 Unit-2 is operating in Mode 4 with the following initial conditions:

• Shutdown to Mode 5 in progress

• Shutdown Cooling (SDC) is in service with 22 LPSI Pump

• RCS pressure is 240 PSIA and steady

• RCS temperature is 250° F and slowly lowering

• 21 LPSI Pump is tagged out The following events occur:

• 22 LPSI Pump trips

• AOP-3B, Abnormal Shutdown Cooling Conditions, is implemented Which ONE of the following actions are required to restore SDC using the Containment Spray system?

A. RCS pressure must be lowered to <170 PSIA; then a Containment Spray pump can be immediately started to restore SDC flow.

B. RCS pressure must be lowered to <170 PSIA; then a Containment Spray pump must be mechanically aligned to SDC before restoring SDC flow.

C. RCS pressure can remain at 240 PSIA; A Containment Spray pump must be mechanically aligned to SDC before restoring SDC flow.

D. RCS pressure can remain at 240 PSIA; A Containment Spray pump can be immediately started to restore SDC flow.

Answer B Answer Explanation A. Incorrect - The first part is correct as stated below. The second part is incorrect but plausible if Operator believes TS requires CS remain in service until Mode 5 is reached (remain operable in Modes 1-4) like Containment TS requires.

B. Correct - With the loss of the single available LPSI pump, a SDC flowpath is still available since this is not a common mode failure. A CS pump is able to restore SDC flow provided RCS pressure is <170 PSIA (to protect CS piping) and the CS pump is Test ID: 340926 02/04/2021 68 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key mechanically aligned to SDC (since its discharge valve will normally be shut on SDC and the LPSI normal suction will need to be opened if on SDC to connect the CS to the SDC suction piping.)

C. Incorrect - First part is incorrect but plausible since AOP-3B allows the starting of a LPSI pump (if one were available) to restore SDC flow and Operator believes same action applies to CS pump. The second part is correct as described above.

D. Incorrect - First part is incorrect but plausible since AOP-3B allows the starting of a LPSI pump (if one were available) to restore SDC flow and Operator believes same action applies to CS pump. The second part is incorrect but plausible as described above.

Question Information Topic RECALL the steps per AOP-3B for restoring SDC flow when neither LPSI pump is available.

User ID Q2155924 System ID 2155924 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-3B, Rev 02800 Training Objective Given plant parameters, determine required actions in accordance with AOP-3B.

Previous NRC Exam Use None References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information Test ID: 340926 02/04/2021 69 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key K/A Reference(s)

SF4.005.A2.01 Safety Function 4 Tier 2 Group 1 RO Imp: 2.7 SRO Imp: 2.9*

Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 70 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 31 ID: 2161285 Points: 1.00 Unit-1 is operating in Mode 4 with the following initial conditions:

Maintenance Outage in progress SDC being placed in service 1-SI-651-MOV, SDC HDR RETURN ISOL, is full open RO is opening 1-SI-652-MOV, SDC HDR RETURN ISOL, with the MOV currently in the intermediate position The following transient occurs:

A loss of MCC-104 Which ONE of the following is the expected initial MOV response?

A. 1-SI-651-MOV remains full open; 1-SI-652-MOV stops opening and remains in the intermediate position.

B. 1-SI-651-MOV remains full open; 1-SI-652-MOV stops opening and starts closing.

C. 1-SI-651-MOV starts closing; 1-SI-652-MOV stops opening and starts closing.

D. 1-SI-651-MOV starts closing; 1-SI-652-MOV stops opening and remains in the intermediate position.

Answer A Answer Explanation A. Correct. Per OI-27D and 60731SH0002, 1-SI-651-MOV is powered from MCC-114 and does not lose power so will remain full open. 1-SI-652-MOV is powered from MCC-104 and fails as is.

B. Incorrect. The first part is correct for 1-SI-651-MOV as stated above. The second part for 1-SI-652-MOV closing is incorrect but plausible if candidate misinterprets the impact of a loss of power with the impact of a high pressure condition which does feedback and change the position of the valve.

C. Incorrect. The first part for 1-SI-651-MOV closing is incorrect but plausible if candidate misinterprets that since the valves have an interlock to shut that they are also Test ID: 340926 02/04/2021 71 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key linked together and with one valve going shut the pressure will build and make the other valve also shut. MOV-652 closing is plausible if candidate misinterpreted the impact of a loss of power with the impact of a high pressure conditions which does feedback and change the position of the valve.

D. Incorrect. The first part for 1-SI-651-MOV closing is incorrect but plausible if candidate misinterprets that since the valves have an interlock to shut that they are also linked together and with one valve not going full open the other will shut to match. The second part for 1-SI-652-MOV is correct since it is powered from MCC-104 and fails as is.

Question Information Topic Shutdown cooling MOV power supplies User ID Q2161285 System ID 2161285 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # 60731SH0002, Rev 51 OI-27D-2, Rev 02300 Training Objective Given a loss of power or air determine the designed impact on operations for the following valves: SCD return header MOVs.

Previous NRC Exam Use None K/A Reference(s)

SF4.005.K2.03 Safety Function 4 Tier 2 Group 1 RO Imp: 2.7* SRO Imp: 2.8*

Knowledge of bus power supplies to the following: (CFR: 41.7)

RCS pressure boundary motor-operated valves Test ID: 340926 02/04/2021 72 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 73 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 32 ID: 2156063 Points: 1.00 Unit-1 is operating at 100% power:

An RCS leak occurs SIAS actuates Which one of the following correctly completes the statements below?

Minimum flow is procedurally maintained in the control room when the HPSI pumps start by ensuring the mini-flow return to the RWT isolation valves, SI-659-MOV and SI-660-MOV, are OPEN with the SI Pump Recirc Lockout Switch in ___(1)___.

And, The minimum flow required for HPSI pumps is ___(2)___.

A. (1) ON (2) 30 GPM B. (1) ON (2) 50 GPM C. (1) LOCKOUT (2) 30 GPM D. (1) LOCKOUT (2) 50 GPM Answer C Answer Explanation A. Incorrect. (1) See below. (2) Correct.

B. Incorrect. (1) Plausible if the candidate misinterprets what lockout refers to and thinks this is the position for post RAS and On is the normal position of this switch in the control room. (2) Plausible if the candidate recognizes that 50 gpm is the minimum flow value for one of the ECCS pumps (Containment Spray pumps) and would then incorrectly conclude that this value is associated with the HPSI pumps.

C. Correct. (1) Per 1C09, TS requires MOVs 659 and 660 to be open with the lockout switch in Lockout during normal operations. (2) Per USFAR, HPSI minimum flow is 30 Test ID: 340926 02/04/2021 74 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key GPM.

D. Incorrect. (1) Correct. (2) See above.

Question Information Topic HPSI pump protection upon SIAS start User ID Q2156063 System ID 2156063 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.8 Components, capacity, and functions of emergency systems.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # 1C09-ALM, Rev 03700 USFAR, table 6.3 6-1, Rev 49 Training Objective Recall from memory the purpose/function of the following: HPSI.

Previous NRC Exam Use None K/A Reference(s)

SF3.006.A1.01 Safety Function 3 Tier 2 Group 1 RO Imp: 3.1 SRO Imp: 3.4 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5 / 45.5)

Avoidance of thermal and pressure stresses due to pump startup Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 75 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 33 ID: 2162517 Points: 1.00 Unit-1 is operating at 100% power when the following transient occurs:

1-RC-404-ERV, PORV momentarily lifts in response to a loss of turbine load The following alarm annunciator is received:

Quench Tank Parameters after stabilization are as follows:

Temperature 133°F Pressure 6 PSIG Level 28 inches (1) What is the expected status of the alarm?

And, (2) What section of OI-1B, Quench Tank Operations, will the Operator use to address this condition?

A. (1) NOT In Alarm (2) Bleed and Feed to cool the Quench Tank B. (1) In Alarm (2) Bleed and Feed to cool the Quench Tank C. (1) In Alarm (2) Purging the Quench Tank with Nitrogen to the Waste Gas System D. (1) NOT In Alarm (2) Purging the Quench Tank with Nitrogen to the Waste Gas System Answer B Answer Explanation A. Incorrect. (1) Incorrect but plausible as stated below. (2) Correct as stated below.

B. Correct. (1) Correct per the 1C06 Alarm Manual which states the alarm actuates Test ID: 340926 02/04/2021 76 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key when QT temperature is >120°F and would still be in alarm. (2) Correct since draining and filling the QT is the method performed in OI-1B to cool the QT.

C. Incorrect. (1) Correct as stated above. (2) Incorrect but plausible since the pressure is above normal operating conditions and a lifted PORV would increase the hydrogen concentration from the RCS and pressure in the tank.

D. Incorrect. (1) Incorrect but plausible if the candidate misinterprets the alarm setpoints for any of the listed parameters and would then conclude the alarm is still in. (2)

Incorrect but plausible as stated above.

Question Information Topic Quench Tank operations after a discharge from PORV User ID Q2162517 System ID 2162517 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # 1C06, Rev 05300 OI-1B, Rev 1705 Training Objective Recall the operation and basis of the following in relation to the RCS in accordance with the Tech Specs, UFSAR, and Operating Procedures:

Previous NRC Exam Use None References Provided Embedded Reference K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information K/A Reference(s)

P2.4.46 Safety Function 3 Tier 3 Group RO Imp: 4.2 SRO Imp: 4.2 Ability to verify that the alarms are consistent with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3 / 45.12)

Test ID: 340926 02/04/2021 77 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key GS.3.0.SF5.007 Safety Function 5 Tier 2 Group 1 RO Imp: SRO Imp:

Pressurizer Relief Tank/Quench Tank System (PRTS)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 78 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 34 ID: 2156103 Points: 1.00 Which of the following are the power supplies 23 Component Cooling Pump?

A. 21A and 21B 480V Buses B. 22A and 23A 480V Buses C. 23B and 24A 480V Buses D. 21B and 24B 480V Buses Answer D Answer Explanation A. Incorrect. Plausible if the operator recalls that 23 Component Cooling Pump can be powered from 2 separate safety related power supplies.

B. Incorrect. Plausible if the operator recalls that 23 CC Pump can be aligned to 2 different Load Centers located in separate Switchgear Rooms and may conclude that 22A and 23A 480V Buses are the correct power supplies.

C. Incorrect. Plausible if the candidate misinterprets that the swing pump would be powered from both an A and B power supply.

D. Correct. Per OI-27D, 23 CC pump can be powered from 21B and 24B 480V buses.

Question Information Topic 23 CC pump electrical power supplies User ID Q2156103 System ID 2156103 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Test ID: 340926 02/04/2021 79 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # OI-27D-2, Rev 02300 OI-16, Rev 03500 Training Objective From memory, describe the physical connections and interrelationships with the CCW system and the following systems without error: 480 VAC Electrical Distribution.

Previous NRC Exam Use None K/A Reference(s)

SF8.008.K2.02 Safety Function 8 Tier 2 Group 1 RO Imp: 3.0* SRO Imp: 3.2*

Knowledge of bus power supplies to the following: (CFR: 41.7)

CCW pump, including emergency backup Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 80 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 35 ID: 2161307 Points: 1.00 Unit-1 is at 100% power:

1-PIC-100X is the in service pressure controller 1-PT-100X fails to 2150 PSIA Which one of the following describes:

(1) The response of Pressurizer temperature?

And (2) The response of Backup Heaters?

A. (1) Temperature rises (2) Automatically energize B. (1) Temperature rises (2) Do NOT automatically energize C. (1) Temperature lowers (2) Do NOT automatically energize D. (1) Temperature lowers (2) Automatically energize Answer A Answer Explanation A. Correct - (1) Sensed pressure is below setpoint therefore proportional heaters fire fully causing the temperature in PZR to rise. (2) Correct since the PZR Backup Heaters automatically energize at 2200 psia PZR pressure.

B. Incorrect - (1) Correct. (2) See below.

C. Incorrect - (1) Plausible if the controller response is misinterpreted and spray is thought to actuate. (2) Plausible if the operator misinterprets the automatic action to energize the Backup Heaters occurs concurrent with the E-29 alarm on 1C06 for PZR Ch 100 Pressure which has a setpoint of 2100 psia.

D. Incorrect - (1) See above. (2) Correct.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic PZR response to a failed PT User ID Q2161307 System ID 2161307 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.3 Mechanical components and design features of the reactor 10CFR55 Content primary system.

10CFR55 Content CFR: 41.8 Components, capacity, and functions of emergency systems.

NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # 1C05-ALM, Rev 04101 Training Objective Given plant conditions, determine if Pressurizer heaters and/or spray are operating properly.

Previous NRC Exam Use 2014 NRC RO References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information K/A Reference(s)

SF3.010.K6.01 Safety Function 3 Tier 2 Group 1 RO Imp: 2.7 SRO Imp: 3.1 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: (CFR: 41.7 / 45.7)

Pressure detection systems Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links Table: TRAINING-QUESTION-AN-OPS-Safety Functions 08 - Plant Service Systems Test ID: 340926 02/04/2021 82 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 36 ID: 2155984 Points: 1.00 Which of the following statements describes the response of the variable pressure signal (Pvar) input to TM/LP setpoint as ASI changes on Unit 1?

A. Pvar increases as ASI changes from -.5 to -.2.

B. Pvar decreases as ASI approaches optimum ASI (0).

C. Pvar remains constant as ASI changes from +.2 to +.5.

D. Pvar remains constant as ASI approaches optimum ASI (0).

Answer B Answer Explanation A. Incorrect. Plausible if the candidate misinterprets the Pvar setpoint diagram as shown in the COLR and misinterprets the inputs to the setpoint calculation.

B. Correct. Per OI-6, the optimum ASI means that there is the least variation from expected power levels, which moves Pvar closest to actual pressure values (decreases).

C. Incorrect. Plausible if the candidate misinterprets the magnitude of the inputs to the Pvar calculation and may conclude that a positive ASI has no impact on Pvar.

D. Incorrect. Plausible if the candidate misinterprets the COLR Pvar figures and the Pvar calculation and may conclude the setpoint remains constant as ASI gets closer to zero.

Question Information Topic What describes the response of(Pvar) input to TM/LP setpoint as ASI changes User ID Q2155984 System ID 2155984 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Test ID: 340926 02/04/2021 83 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # COLR Cycle 25 OI-6, Rev 01901 Training Objective Recall the Inputs to the PVAR Calculator and project the impact of Increasing or Decreasing Values of those Inputs on the Calculated Value of PVAR.

Previous NRC Exam Use None K/A Reference(s)

SF7.012.A1.01 Safety Function 7 Tier 2 Group 1 RO Imp: 2.9* SRO Imp: 3.4*

Ability to predict and/or monitor Changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including: (CFR: 41.5 / 45.5)

Trip setpoint adjustment Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 84 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 37 ID: 2161312 Points: 1.00 Unit-1 is at 100% power when a malfunction occurs in RPS Channel B causing the Power Trip Test Interlock (PTTI) to actuate.

Given the following:

CMI = CEA Motion Inhibit CWP = CEA Withdrawal Prohibit Which ONE of the following describes the effect on the Control Rod Drive System?

A. 1 of 2 required pre-trips for CMI is met.

B. 1 of 4 required pre-trips for CWP is met.

C. 1 of 2 required pre-trips for CWP is met.

D. 1 of 4 required pre-trips for CMI is met.

Answer C Answer Explanation A. Incorrect. Plausible if the candidate misinterprets which CEA circuitry (CMI vs CWP) is impacted from PTTI.

B. Incorrect. Plausible if the candidate misinterprets that CWP requires all 4 channels to actuate like other RPS functions.

C. Correct. Per 1C05, PTTI will provide 1 of 2 required pre-trips to CWP circuit to prevent outward movement of CEAs.

D. Incorrect. Plausible if the candidate misinterprets which CEA circuitry (CMI vs CWP) is impacted from PTTI and the required logic.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Effect of PTTI occurring to CEAs User ID Q2161312 System ID 2161312 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.6 Design, components, and functions of reactivity control 10CFR55 Content mechanisms and instrumentation.

CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # 1C05-ALM, Rev Training Objective Determine the effect on the Control Rod Drive System when the Power Trip Test Interlock occurs.

Previous NRC Exam Use 2012 NRC RO K/A Reference(s)

SF7.012.K3.01 Safety Function 7 Tier 2 Group 1 RO Imp: 3.9 SRO Imp: 4.0 Knowledge of the effect that a loss or malfunction of the RPS will have on the following: (CFR: 41.7 / 45.6)

CRDS Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 86 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 38 ID: 2156086 Points: 1.00 Unit-2 is operating at 100% power:

ESFAS Logic cabinet "BL" has been deenergized to support emergent maintenance.

What effect, if any, will this condition have on the Reactor Protective System and/or Main Turbine Trips?

A. A Reactor trip will NOT cause a Turbine trip.

B. The RPS/Turbine trip interface will function normally.

C. 2 out of 4 RPS trips on Loss of Load will cause a Turbine trip.

D. Turbine trip logic is reduced to 2 out of 2 Reactor Trip Bus U/V relay actuations.

Answer A Answer Explanation A. Correct. Per OI-34, De-energization of the BL Actuation Logic Cabinet renders the Reactor Trip Bus UV turbine trips inoperable.

B. Incorrect. Plausible if the candidate misinterprets that the turbine trip function is accomplished by both the A and B logic cabinets and determines it will function normally like most other ESFAS functions.

C. Incorrect. Plausible if the candidate misinterprets that the turbine trip function is accomplished from the A logic cabinet only.

D. Incorrect. Plausible if the candidate misinterprets how the logic will change on a loss of a logic cabinet coupled with the fact that the turbine trip function is only accomplished from one logic cabinet.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic RPS/TG ESFAS interrelationship User ID Q2156086 System ID 2156086 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification Candidate must understand the definition of channel with regards to the RPS and MT trip logic and apply this definition to the noted conditions to determine the impact on the systems.

SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # OI-34, Rev 00100 Training Objective Evaluate plant conditions and/or parameters and determine the following, in accordance with ESFAS related drawings and procedures: Operator action required.

Previous NRC Exam Use None K/A Reference(s)

SF2.013.K5.01 Safety Function 2 Tier 2 Group 1 RO Imp: 2.8 SRO Imp: 3.2 Knowledge of the operational implications of the following concepts as they apply to the ESFAS: (CFR: 41.5 / 45.7)

Definitions of safety train and ESF channel Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 88 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 39 ID: 2161317 Points: 1.00 Unit-1 is operating at 100% power when the following sequence of events occurs:

Time 10:00:00 11 S/G Pressure is 860 PSIA 12 S/G Pressure is 860 PSIA 11 S/G Level is 0 inches 12 S/G Level is 0 inches Time 10:01:00 11 S/G Pressure is 856 PSIA 12 S/G Pressure is 740 PSIA 11 S/G Level is minus (-) 120 inches 12 S/G Level is minus (-) 175 inches Time 10:02:30 11 SG Pressure is 800 PSIA 12 SG Pressure is 740 PSIA 11 SG Level is minus (-) 100 inches 12 SG Level is minus (-) 180 inches Assuming NO operator actions, what is the current status of Auxiliary Feed Water?

A. AFW is supplying 11 S/G ONLY B. AFW is supplying 12 S/G ONLY C. AFW is supplying neither S/G D. AFW is supplying 11 & 12 S/G Answer D Answer Explanation A. Incorrect. Plausible if the candidate misinterprets that the block signal will lock in and not clear meaning that AFW will only supply 11 SG.

B. Incorrect. Plausible if the candidate misinterprets that only the SG with the level below the AFAS signal will receive feed from AFW.

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Exam Material 2021 ILT NRC RO EXAM Test Key C. Incorrect. Plausible if the candidate misinterprets that only the S/G with the level below the AFAS signal will receive feed and that the block signal locks in and does not clear.

D. Correct. Per 1C03, AFAS has initiated based on the setpoint of (-) 170 inches in at least one S/G for 20 seconds. At time 10:01, there is an AFAS Block to 12 S/G for having a lower pressure than 11 S/G that is greater than the setpoint of 115 psid. Then at time 10:02:30, the AFAS Block will automatically clear since the pressure difference is no longer greater than the setpoint of 115 psid. AFW is supplying flow to both S/Gs after the AFAS block cleared.

Question Information Topic AFAS/ AFAS block with no operator action User ID Q2161317 System ID 2161317 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

References Provided None K/A Justification This question matches the K/A by asking the candidate to identify the logic and redundancy of the indications that cause an AFAS actuation and what Steam Generators will receive AFW flow. The candidate will demonstrate knowledge that the reliability of a low level in only one SG will provide AFW flow to both SGs.

SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # 1C03-ALM, Rev 06000 Training Objective Explain the initiating plant conditions and predict the AFAS response actions for the following: AFAS Start and AFAS Block.

Previous NRC Exam Use 2012 NRC RO Test ID: 340926 02/04/2021 90 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key K/A Reference(s)

SF2.013.K5.02 Safety Function 2 Tier 2 Group 1 RO Imp: 2.9 SRO Imp: 3.3 Knowledge of the operational implications of the following concepts as they apply to the ESFAS: (CFR: 41.5 / 45.7)

Safety system logic and reliability Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 91 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 40 ID: 2156384 Points: 1.00 Unit-1 is operating normally at 100% power when:

A Loss of Offsite Power occurs 1A DG fails to start All other plant equipment responds as designed In this condition, which of the following Containment Air Coolers remain powered?

A. 11 and 12 B. 11 and 13 C. 12 and 14 D. 13 and 14 Answer D Answer Explanation A. Incorrect. Plausible if the power supplies for 11 and 12 CAC are misinterpreted to be from the "B" train.

B. Incorrect. Plausible if the power supply for 11 CAC is misinterpreted to be from "B" train. 13 is powered from B train.

C. Incorrect. Plausible if examinee thinks that even numbered CACs are powered from the "B" train since most even number components are B train powered.

D. Correct. Per OI-27D, 13 and 14 CACs normal power supply is "B" train which would be repowered from the 1B DG after a LOOP.

Test ID: 340926 02/04/2021 92 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Recall the power supplies for the Containment Coolers User ID Q2156384 System ID 2156384 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-7I-1 Rev 03400 OI-27D-2, Rev 02300 Training Objective Identify the power supplies for the following components:

Containment Spray Pumps and Containment Air Coolers.

Previous NRC Exam Use Modified from a question on NRC RO Exam - July 2002 References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information K/A Reference(s)

SF5.022.K2.01 Safety Function 5 Tier 2 Group 1 RO Imp: 3.0* SRO Imp: 3.1 Knowledge of power supplies to the following:(CFR:41.7)

Containment cooling fans Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 93 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 41 ID: 2161280 Points: 1.00 Unit-1 reactor tripped due to a Steam Line Rupture inside Containment All expected ESFAS signals automatically actuated All containment parameters have returned to normal levels The CRO is performing EOP-4 Block Step S, Reset ESFAS Actuations.

Which one of the following describes:

(1) Containment Spray Flow should be _______ per pump prior to resetting?

And, (2) Actions required to reset the CSAS signal are _______.

A. (1) 675 gpm (2) Match handswitches and then depress both CSAS reset pushbuttons B. (1) 675 gpm (2) Match handswitches, block the CSAS signal, and then depress both CSAS reset pushbuttons C. (1) 1350 gpm (2) Match handswitches and then depress both CSAS reset pushbuttons D. (1) 1350 gpm (2) Match handswitches, block the CSAS signal, and then depress both CSAS reset pushbuttons Answer C Answer Explanation A. Incorrect. (1) See below. (2) Correct.

B. Incorrect. (1) Plausible if the candidate misinterprets the correct value of 1350 gpm per pump to be the total flow for both running Containment Spray Pumps and concludes there is 675 gpm per pump. Also, plausible if the candidate misinterprets that CS flow will lower as containment pressure lowers since less water flow is required to recover.

(2) Plausible is the candidate misinterprets that CSAS signal has a block function like SGIS and SIAS and would require the block in to be able to reset.

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Exam Material 2021 ILT NRC RO EXAM Test Key C. Correct. (1) Per EOP-4, CS flow should be 1350 gpm per pump. (2) Per EOP-4, CSAS signal does not have a block function so only the required handswitches have to be matched and then the reset pushbuttons pressed.

D. Incorrect. (1) Correct. (2) See above.

Question Information Topic CSAS Flow and reset logic User ID Q2161280 System ID 2161280 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-4, Rev 19 EOP-ATT, Rev 23 Training Objective Recall the operation of ESFAS including reset signals.

Previous NRC Exam Use None K/A Reference(s)

SF5.026.A4.05 Safety Function 5 Tier 2 Group 1 RO Imp: 3.5 SRO Imp: 3.5 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)

Containment spray reset switches Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 95 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 42 ID: 2156388 Points: 1.00 Unit-1 is operating at 100% power:

12 Component Cooling Water (CCW) pump is out of service Then, a Large Break LOCA occurs:

11 Containment Spray (CS) pump fails to start 1-SI-657-CV (SDC HX Temp Control) fails shut Which one of the following actions, if any, is required to maintain the containment peak pressure and temperature below design limits 20 minutes into the LOCA event?

A. The current system alignment is adequate.

B. The 11 CS pump must be restored to service.

C. The 12 CCW pump must be restored to service.

D. The SDC temperature control valve (1-SI-657-CV) must be manually opened.

Answer A Answer Explanation A. Correct. Per Tech Specs, during a DBA, a minimum of one containment cooling train and one containment spray train, is required to maintain the containment peak pressure and temperature, below the design limits. The 11/12 CACs and 12 CS pumps are operable and adequate to remove emergency heat loads.

B. Incorrect. Plausible if the candidate misinterprets that the 12 CS pump is not operable due to the loss 1-SI-657 cooling to the SDC HX and then would need 11 CS pump to restore adequate cooling.

C. Incorrect. Plausible if the candidate misinterprets that 12 CC pump has to be restored to call 12 CS pump operable but CC is cross-connected.

D. Incorrect. Plausible if the candidate misinterprets that the failure of the 1-SI-657 causes a common mode failure in the SDC heat exchangers - note that 1-SI-657 (SDC temperature control valve) controls CCW discharge flow in a common discharge line when in shutdown cooling. If this valve was in the SI recirculation flow path, it could potentially block both coolers. But this valve is bypassed during safety injection.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Minimum Spray Pp and CACs cooling during DBA LOCA User ID Q2156388 System ID 2156388 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification The question matches the K/A and requires the candidate to evaluate the provided conditions and failures and determine the total impact to the Containment Spray system.

SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # TS 3.6.6 Basis Training Objective Given a set of plant conditions, correctly apply the requirements of the TS.

Previous NRC Exam Use 2006 NRC RO K/A Reference(s)

SF5.026.K3.02 Safety Function 5 Tier 2 Group 1 RO Imp: 4.2* SRO Imp: 4.3 Knowledge of the effect that a loss or malfunction of the CSS will have on the following: (CFR: 41.7 / 45.6)

Recirculation spray system Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 97 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 43 ID: 2161403 Points: 1.00 Unit 1 is operating at 40% power, MOC, when the following occurs:

1-PT-4056, MS Turb Bypass VLV Controller process variable, fails to 950PSIA NO operator action is taken What is the impact on Unit-1?

A. Reactor power lowers and stabilizes at a lower value.

B. Reactor power lowers and then the reactor automatically trips.

C. Reactor power rises and then the reactor automatically trips.

D. Reactor power rises and stabilizes at a higher value.

Answer C Answer Explanation A. Incorrect. Plausible if MTC is believed to be positive at low power levels and the TBVs opening will cause RCS Temperature to lower which will cause reactor power to lower.

B. Incorrect. Plausible if MTC is believed to be positive at low power levels and the TBVs opening will cause RCS Temperature to lower which will cause reactor power to lower and continue to lower causing a reactor trip on TM/LP.

C. Correct. The failure of the PT will cause the Process Variable to fail to 950 PSIA which is above the setpoint of 900 causing the TBVs to Open. Since the PV is failed the TBVs will continue to open until the controller is at 100% (all 4 TBVs open). The TBVs failing open will lower RCS Temperature which will cause Reactor Power to Rise

~40%, which is above the VOPT setpoint of 8% above the current power level.

D. Incorrect. TBVs will raise power approximately 40% which is above the VOPT setpoint of ~8% above current power. Plausible if VOPT trip is thought to only occur at higher power levels (VOPT is activated for power greater than 30%).

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic PT-4056 Failure and impact on RCS User ID Q2161403 System ID 2161403 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-7K, Rev 3 60911SH0001, Rev 13 Training Objective Given plant conditions, indications, and events in progress, evaluate the impact of the event on the following: Reactor Power.

Previous NRC Exam Use None K/A Reference(s)

SF4.039.A2.04 Safety Function 4 Tier 2 Group 1 RO Imp: 3.4 SRO Imp: 3.7 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

Malfunctioning steam dump Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 99 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 44 ID: 2156391 Points: 1.00 Unit-2 is escalating in power, recovering from a mid-cycle forced outage.

The reactor is at approximately 50% power with 21 SGFP in operation.

22 SGFP is out of service for maintenance.

Under these conditions, which one of the following sets of parameters on 21 SGFP would allow continued one pump operation at the current power level?

A. Suction flow: 15,200 GPM; Turbine speed: 5060 RPM; Suction pressure: 242 PSIG B. Suction flow: 16,200 GPM; Turbine speed: 5080 RPM; Suction pressure: 262 PSIG C. Suction flow: 17,200 GPM; Turbine speed: 5335 RPM; Suction pressure: 272 PSIG D. Suction flow: 18,200 GPM; Turbine speed: 5260 RPM; Suction pressure: 252 PSIG Answer B Answer Explanation A. Incorrect - Suction pressure is below the stated operating limit of 250 PSIG.

Plausible since this value is above the SGFP suction pressure trip of 221 psig.

B. Correct - Per the Precautions stated in OI-12A-2. Per the Precautions stated in OI-12A-2 one pump operation is permitted if all of the following conditions are maintained:

Suction flow rate below 18,000 GPM, Turbine speed below 5100 RPM, Suction pressure above 250 PSIG.

C. Incorrect - SGFP speed is above the stated operating limit of 5100 RPM. Plausible because speed is within the operating range for a Unit-1 SGFP.

D. Incorrect - SGFP speed is above the stated operating limit of 5100 RPM and SGFP suction flow rate is also above the limit for single pump operation. Plausible because Test ID: 340926 02/04/2021 100 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key speed is within the operating range for a Unit-1 SGFP.

Question Information Topic Operating limitations on Unit-2 SGFPs User ID Q2156391 System ID 2156391 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # OI-12A-2, Rev 05101 Training Objective Given plant conditions and/or parameters determine if SGFP operating limitations are exceeded.

Previous NRC Exam Use RO - August 2012 References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information K/A Reference(s)

SF4.059.A1.03 Safety Function 4 Tier 2 Group 1 RO Imp: 2.7* SRO Imp: 2.9*

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including: (CFR: 41.5/45.5)

Power level restrictions for operation of MFW pumps and valves.

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 101 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 45 ID: 2161405 Points: 1.00 Unit-1 is operating at 100%

A reactor trip occurs due to an RPS malfunction The 11 Main Feed Regulating Valve fails full open on the trip EOP-0, Post Trip Immediate Actions is implemented Which of the following describes the required actions for Core and RCS Heat Removal per EOP-0?

A. Reset the reactor trip override on Ovation B. Trip 11 SGFP only, place 11 CBP in PTL, place 11 CP in PTL C. Start an AFW Pump, trip both SGFPs, shut the SG Feedwater Isolation Valves D. Trip both SGFPs, place CBPs in PTL, shut the Main Steam Isolation Valves, start an AFW Pump Answer C Answer Explanation A. Incorrect. Plausible if the candidate misinterprets that resetting the RTO signal resolves the failed open MFRV (like it could for a failed open BFRV). But, incorrect since the MFRV will remain failed open and will overfeed the S/G.

B. Incorrect. Plausible is the candidate misinterprets that securing the 11 main feed water components will stop the flow through 11 MFRV. But incorrect since there will still be an overfeed condition to 11 S/G from 12 SGFP.

C. Correct. Per EOP-0, if feed is excessive the procedure directs starting an AFW pump, tripping both SGFPs, and shutting the SG Feedwater Isolation valves.

D. Incorrect. Plausible if the candidate misinterprets the required steps from AOP-3G for a feedwater rupture since both would have more feedwater flow than normal. But Test ID: 340926 02/04/2021 102 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key incorrect since the alternate action required does not include shutting the MSIVs or securing the Condensate Booster Pumps.

Question Information Topic Overfeed actions in EOP-0 User ID Q2161405 System ID 2161405 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-00-2, Rev 1500 Training Objective Given plant conditions associated with various Feedwater malfunctions, the license operator candidate will be able to correctly recall and/or identify the proper response and bases to successfully mitigate the effects of Feedwater malfunctions.

Previous NRC Exam Use None K/A Reference(s)

SF4.059.K1.02 Safety Function 4 Tier 2 Group 1 RO Imp: 3.4* SRO Imp: 3.4 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

AFW system Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 103 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 46 ID: 2156405 Points: 1.00 Unit-1 is at EOC:

STP-O-073H, AFW Pump Large Flow Test is being performed Power is at the required level per the STP 13 AFW Pump is about to be started Which of the following describes:

(1) The impact on Tcold while 13 AFW pump is running?

And, (2) Why?

A. (1) Tcold rises (2) due to added feedwater flow ONLY B. (1) Tcold rises (2) due to added feedwater flow and steam demand C. (1) Tcold lowers (2) due to added feedwater flow and steam demand D. (1) Tcold lowers (2) due to added feedwater flow ONLY Answer D Answer Explanation A. Incorrect. (1) See below. (2) Correct.

B. Incorrect. (1) Plausible if the candidate misinterprets EOC MTC and how colder AFW water will impact the RCS. (2) Plausible if the candidate misinterprets that 13 AFW pump being running will also increase the steam demand based on added electrical load or misinterprets how 13 AFW is powered.

C. Incorrect. (1) Correct. (2) See above.

D. Correct. (1) Per STP-O-073H, Tcold will lower about 1° during the test. (2) Per STP-O-073H, only running the steam driven AFW pumps will increase steam demand and 13 Test ID: 340926 02/04/2021 104 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key AFW is motor driven.

Question Information Topic AFW Large Flow Test impact on RCS User ID Q2156405 System ID 2156405 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # STP O-073H-1, Rev 01200 Training Objective State the set points, possible causes, automatic actions, and required operator actions associated with the AFW system.

Previous NRC Exam Use None K/A Reference(s)

SF4.061.K5.01 Safety Function 4 Tier 2 Group 1 RO Imp: 3.6 SRO Imp: 3.9 Knowledge of the operational implications of the following concepts as the apply to the AFW: (CFR: 41.5 / 45.7)

Relationship between AFW flow and RCS heat transfer Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 105 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 47 ID: 2161406 Points: 1.00 Unit-1 is in a refueling outage MCC 104 normal feeder breaker requires maintenance Which of the following completes the statement:

Per procedure, MCC 104 will be tied to MCC ___(1)___ using a ___(2)___ bus transfer.

A. (1) 114 (2) live B. (1) 114 (2) dead C. (1) 204 (2) dead D. (1) 204 (2) live Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

B. Correct. (1) Per OI-27D, MCC 104 is tied to MCC 114. (2) Per OI-27D, safety related MCCs are tied using a dead bus transfer.

C. Incorrect. (1) See below. (2) Correct.

D. Incorrect. (1) Plausible if the candidate understands the separation of A and B power trains and determines that by tying to a B train power supply on Unit-2, the separation will still be maintained which would meet the requirements of the Tech Specs. (2)

Plausible if the candidate misinterprets that since these buses are safety related, it is required to maintain them powered at all times for operational and Tech Spec concerns.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic How to tie MCC 104 User ID Q2161406 System ID 2161406 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 2 Technical Reference and Revision # OI-27D-1, Rev 01400 Training Objective State which MCCs require dead bus transfer of supply power, and the method of preventing a live bus transfer.

Previous NRC Exam Use None K/A Reference(s)

SF6.062.A2.05 Safety Function 6 Tier 2 Group 1 RO Imp: 2.9 SRO Imp: 3.3*

Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

Methods for energizing a dead bus Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 107 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 48 ID: 2156407 Points: 1.00 While touring the 45 foot Switchgear Room, the TBO reports:

White Load Shed Verification Light is lit on 4KV Bus 14 Which one of the following is that status of the Load Shed Verification Relays, and the reason for the status?

A. Load Shed Verification Relays will NOT function correctly, because either the normal or alternate feeders to 4KV Bus 14 are closed B. Load Shed Verification Relays will NOT function correctly, because both the normal and alternate feeders to 4KV Bus 14 are open C. Load Shed Verification Relays will function correctly, because either the normal or alternate feeders to 4KV Bus 14 are closed D. Load Shed Verification Relays will function correctly, because both the normal and alternate feeders to 4KV Bus 14 are open Answer C Answer Explanation A. Incorrect. White lights are normally on, indicating that the load shed relays are deenergized. As long as either the normal or alternate feeders for 14 4KV bus are closed, this is the normal condition. Plausible if candidate misinterprets that relays in the plant are normally energized.

B. Incorrect. Relays would be energized with both feeder breakers open, but light would be out. Plausible if candidate misinterprets that relays in the plant are normally energized and that the load shed verification is lit when a load shed should have occurred due to both breakers open but did not.

C. Correct. Per drawings, light is normally lit, indicating that either the normal or alternate power supply breaker is on the bus. Relays are normally de-energized.

D. Incorrect. Both feeder breakers being open would cause the white light to be extinguished. Plausible if candidate misinterprets that the load shed verification light is lit when a load shed has occurred with both breakers to the bus open.

Test ID: 340926 02/04/2021 108 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic How load shed verification light works User ID Q2156407 System ID 2156407 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification Questions meets the K/A as it evaluates candidate knowledge of the automatic feature for circuit breaker load shed on the safety related 4KV buses SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # Dwgs 61071sh0007, Rev 19 Dwgs 61071sh0008, Rev 20 Dwgs 61071sh0016, Rev 17 Dwg 61005, Rev 37 Training Objective Describe the 4Kv design features and/or interlocks, including initiating devices, which provide for the following: SR 4Kv bus UV and load shed verification relay circuit.

Previous NRC Exam Use None K/A Reference(s)

SF6.062.K4.03 Safety Function 6 Tier 2 Group 1 RO Imp: 2.8* SRO Imp: 3.1 Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: (CFR:

41.7)

Interlocks between automatic bus transfer and breakers Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 109 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 49 ID: 2161407 Points: 1.00 Unit 1 is in mode 6 conducting a refueling outage:

125 VDC Battery 11 is removed from service for unplanned maintenance.

The reserve battery is not available.

Battery Charger 11 is out of service for maintenance.

120 VAC vital instrument buses are aligned normally.

Battery Charger 13 fails.

No operator actions have been taken.

Which one of the following statements correctly describes the current condition of the 120 Volt Vital AC and/or 125 Volt Vital DC systems?

A. 11 120 Volt Vital AC Instrument Bus (1Y01) is deenergized.

B. 22 120 Volt Vital AC Instrument Bus (2Y02) is deenergized.

C. 11 125 Volt DC Bus is deenergized.

D. No AC or DC buses have been lost.

Answer D Answer Explanation A. Incorrect. 11DC bus will still be powered from 23 charger which will maintain 1Y01 energized. Plausible if student misinterprets the AC/DC vital bus arrangement and determines that 13 charger feeds 1Y01.

B. Incorrect. 2Y02 is powered from 21 DC bus. Plausible if student misinterprets the AC/DC vital bus arrangement and determines that 13 charger feeds 2Y02.

C. Incorrect. 11 DC bus continues to be powered by 23 charger. Plausible if student misinterprets the AC/DC vital bus arrangement and determines that with the loss of 13 charger the 11 DC Bus is lost.

D. Correct. All DC busses remain energized. AOP-7J does not have to entered. No 125 VDC or 120 Vital AC busses have been lost.

Test ID: 340926 02/04/2021 110 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Loss of 11 Battery, 11 Charger and 13 Charger User ID Q2161407 System ID 2161407 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # 61024, Rev 0059 Training Objective State the physical connections and evaluate the relationships between the 125 VDC and 120 VAC distribution systems and the following: 125 VDC Reserve Battery System.

Previous NRC Exam Use None K/A Reference(s)

SF6.063.K1.03 Safety Function 6 Tier 2 Group 1 RO Imp: 2.9 SRO Imp: 3.5 Knowledge of the physical connections and/or cause- effect relationships between the DC electrical system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

Battery charger and battery Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 111 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 50 ID: 2156408 Points: 1.00 Units 1 and 2 are operating at 100% power:

Chemistry samples show extensive diesel fuel oil contamination in 11 and 21 fuel oil storage tanks (FOST)

Chemistry samples show 1A FOST has clean fuel oil Which one of the following statements describes the DGs that can receive clean fuel oil from FOST 1A through the installed fuel oil system?

A. All DGs can be fueled from FOST 1A.

B. Only the 1A DG can be fueled from FOST 1A.

C. Only the 1A and 2A DG can be fueled from FOST 1A.

D. Only the 1A and 0C DGs can be fueled from FOST 1A.

Answer B Answer Explanation A. Incorrect. Plausible if the candidate misinterprets the FO lineups and assumes since the 1A is a protected tank it would make sense that it can be used for all the EDGs.

B. Correct. Per OI-21D, only the 1A EDG can receive fuel from the 1A FOST.

C. Incorrect. Plausible if the candidate misinterprets that the 1A FOST feeds the A train EDGs.

D. Incorrect. Plausible if the candidate misinterprets that since the 1A FOST is in the same shared building as the 1A and 0C it would be able to fuel both EDGs.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic SACM - FO - State the purpose and function of the SACM Diesel Generators Fuel Oil Systems.

User ID Q2156408 System ID 2156408 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # OI-21D, Rev 01200 Training Objective State the purpose and function of the SACM Diesel Generators Fuel Oil Systems.

Previous NRC Exam Use None K/A Reference(s)

SF6.064.K6.08 Safety Function 6 Tier 2 Group 1 RO Imp: 3.2 SRO Imp: 3.3 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 / 45.7)

Fuel oil storage tanks Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 113 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 51 ID: 2161409 Points: 1.00 BD REC HI-TEMP DUMP, 1-BD-4088-CV, is closed SG Blowdown Recovery System Radiation Monitor, RI-4095, alarms Which one of the following describes the automatic action(s), if any, that occur, and any manual operator action(s) required?

A. Blowdown isolation CVs automatically go shut and blowdown recovery automatically shifts to Miscellaneous Waste system.

B. Blowdown recovery automatically shifts to Miscellaneous Waste System and operator action is required to shut SG Blowdown CVs.

C. Blowdown isolation CVs automatically go shut and blowdown recovery automatically shifts to the Circulating Water System.

D. Operator action is required to shut the SG Blowdown CVs and operator action is required to shift blowdown recovery to Miscellaneous Waste.

Answer B Answer Explanation A. Incorrect. Plausible if the candidate misinterprets the actions from RI-4014 the other SG BD RMS.

B. Correct. Per OI-8A, 4095 shifts BD to MWS and manual action will be required to shut the blowdown CVs.

C. Incorrect. Plausible if the candidate misinterprets the actions from RO-4014 and misinterprets where discharge will shift to on a high alarm.

D. Incorrect. Plausible if the candidate misinterprets that blowdown will shift to the circulating water system on a high rad alarm since we normally discharge our liquid waste to the CW system.

Test ID: 340926 02/04/2021 114 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic SG Blowdown Tank Rad Automatic actions when RI-4095 alarms User ID Q2161409 System ID 2161409 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Modified Difficulty 3 Technical Reference and Revision # OI-8A, Rev 05200 Training Objective Evaluate the response of the SG Blowdown and Recovery system for the following conditions: RI-4095 (

SG Blowdown Recovery) in alarm.

Previous NRC Exam Use None K/A Reference(s)

SF7.073.K4.01 Safety Function 7 Tier 2 Group 1 RO Imp: 4.0 SRO Imp: 4.3 Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

Release termination when radiation exceeds setpoint Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 115 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 52 ID: 2156409 Points: 1.00 Which of the following is a purpose of the Service Water (SRW) System?

A. Provide cooling flow to the 1A Diesel Generator.

B. Provide cooling flow to the Containment Penetrations.

C. Provide cooling flow to the Spent Fuel Pool Coolers (HXs).

D. Provide cooling flow to the Shutdown Cooling Heat Exchangers.

Answer C Answer Explanation A. Incorrect. Plausible since all 3 other EDGs are cooled with SRW.

B. Incorrect. Plausible if the candidate misinterprets that since some containment components are cooled by SRW (CACs) that Containment Penetrations are also.

C. Correct. Per OI-15, SRW cools the SFP Heat Exchangers.

D. Incorrect. Plausible if the candidate misinterprets that since SRW pumps have safety system actuation unlike the CC pumps that they would provide cooling to safety components like the SDC HXs.

Question Information Topic Which of the following is a purpose of the Service Water (SRW) System?

User ID Q2156409 System ID 2156409 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information Test ID: 340926 02/04/2021 116 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # OI-15, Rev 04900 Training Objective State from memory the purpose of the SRW system.

Previous NRC Exam Use None K/A Reference(s)

P2.1.27 Safety Function 7 Tier 3 Group RO Imp: 3.9 SRO Imp: 4.0 Knowledge of system purpose and/or function.

(CFR: 41.7)

GS.3.0.SF4.SEC.076 Safety Function 4 Tier 2 Group 1 RO Imp: SRO Imp:

Service Water System (SWS)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 117 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 53 ID: 2161440 Points: 1.00 Which one of the following would be the first indication of an instrument air header leak on Unit 1?

A. Standby Instrument Air compressor starts B. Plant air header automatic isolation valve closes C. "INSTR AIR COMPRESSORS" annunciator alarms D. "PLANT AIR PRESS LO " annunciator alarms Answer A Answer Explanation A. Correct. Per 1C13, the standby air compressor starts at 93 PSIG.

B. Incorrect. Plausible if the candidate remembers that plant air is not essential and determines that this would be the first action to supply backup IA based on incorrectly recalling the actual setpoint that 1-PA-2059-CV shuts.

C. Incorrect. Plausible if the candidate misinterprets that this alarm comes in when the standby IAC starts due to the lowering IA header pressure. The candidate may misinterpret this alarm with the Instrument Air Malfunction alarm that is an early warning when the IA Dryer deenergize at 93 psig.

D. Incorrect. Plausible if the candidate misinterprets that the plant air cross connect valve is the first source of back up air to the IA system since plant air is not required for power operation. When the Plant air header isolation valve closes, it will cause the Plant Air Pressure Low alarm to actuate on lowering plant air header pressure.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Which one of the following would be the first indication of an instrument air header leak on Unit-Topic 1?

User ID Q2161440 System ID 2161440 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # 1C13-ALM, Rev 05600 Training Objective Identify the design features that provide a backup for the instrument air system during a partial or total loss of the system.

Previous NRC Exam Use None K/A Reference(s)

SF8.078.A3.01 Safety Function 8 Tier 2 Group 1 RO Imp: 3.1 SRO Imp: 3.2 Ability to monitor automatic operation of the IAS, including: (CFR: 41.7 / 45.5)

Air pressure Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 119 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 54 ID: 2156783 Points: 1.00 Instrument Air Compressors receive a start signal from the ___(1)___?

And, The ___(2)___ system can be used as a backup method of cooling for the Instrument Air Compressors, per OI-19, Instrument Air?

A. (1) LOCI and the Shutdown Sequencers (2) Fire Main B. (1) LOCI and the Shutdown Sequencers (2) Condensate C. (1) Shutdown Sequencer ONLY (2) Fire Main D. (1) Shutdown Sequencer ONLY (2) Condensate Answer C Answer Explanation A. Incorrect. (1) See below. (2) Correct.

B. Incorrect. (1) Plausible since many components usually supplied by instrument air are required to operate post SIAS (LOCI) and if the LOCI sequencer is misinterpreted to not start the SWACs then the candidate would conclude that IA compressors would get a start signal on both the LOCI and SDS. (2) Plausible since condensate is used to cool many components in the turbine building close to the IA compressors.

C. Correct. (1) Per 61058ASH0001, both instrument air compressors receive start signals from the SDS only, this is due to the loss of SRW on a SIAS (LOCI). (2) Per OI-19, the fire main system can be used to provide backup cooling to the IA compressors.

D. Incorrect. (1) Correct. (2) See above.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Loss of Cooling to IA User ID Q2156783 System ID 2156783 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # OI-19, Rev 03800 61058ASH0001, Rev 0055 Training Objective Evaluate the effect that a loss of service water will have on the compressed air system.

Previous NRC Exam Use None K/A Reference(s)

SF8.078.K1.04 Safety Function 8 Tier 2 Group 1 RO Imp: 2.6 SRO Imp: 2.9 Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

Cooling water to compressor Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

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Exam Material 2021 ILT NRC RO EXAM Test Key Question 55 ID: 2161444 Points: 1.00 Which of the following valves shuts on a Containment Isolation Signal?

A. 1-IA-2080-MOV, IA Containment Isolation Valve B. 1-CPA-1410-CV, Containment Purge Supply Valve C. 1-CRM-5291-CV, Containment RMS Isolation Valve D. 1-CC-3824-CV, CCHX Component Cooling Outlet Valve Answer A Answer Explanation A. Correct. Per EOP-ATT, CIS shuts the IA Containment Isolation Valve.

B. Incorrect. Plausible if the candidate misinterprets the CIS signal actuations with the CRS actuations which both work to isolate containment.

C. Incorrect. Plausible if the candidate misinterprets that since this action occurs at the same setpoint as CIS that it is actuated by CIS but is actuated by SIAS.

D. Incorrect. Plausible if the candidate misinterprets which CC valves are operated by CIS, since CIS does the CC supply and return valves.

Question Information Topic CIS shuts which valve User ID Q2161444 System ID 2161444 Status Active Point Value 1.00 Time (min) 0 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information Test ID: 340926 02/04/2021 122 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-ATT, 02300 Training Objective Recall the initiating ESFAS signals that shut the following valves: CC-3832 & 3833-CVs (Containment CC supply and return).

Previous NRC Exam Use None K/A Reference(s)

SF5.103.A3.01 Safety Function 5 Tier 2 Group 1 RO Imp: 3.9 SRO Imp: 4.2 Ability to monitor automatic operation of the containment system, including: (CFR: 41.7 / 45.5)

Containment isolation Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

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Exam Material 2021 ILT NRC RO EXAM Test Key Question 56 ID: 2156939 Points: 1.00 Unit-2 is operating at 100% power:

A LOCA occurs EOP-5, Loss of Coolant Accident, is implemented RCS pressure is 1285 PSIA CET temperatures are being lowered to ensure subcooling margin What is the MAX CET temperature where the subcooling margin limits will be maintained?

A. 541°F B. 546°F C. 551°F D. 556°F Answer B Answer Explanation A. Incorrect. Plausible if the candidate misinterprets how to convert PSIA to PSIG and how to interpolate in the steam tables (571-30=541).

B. Correct. Per the steam tables, saturation temperature for 1285 PSIA is 576°F. Per EOP-5, subcooling band is 30-140°F (576-30=546).

C. Incorrect. Plausible if the candidate misinterprets the limit for subcooling to be 25-140°F since this is the band for a different casualty (576-25=551).

D. Incorrect. Plausible if the candidate misinterprets the subcooling band with the subcooling limit for RCP operation which is 20°F (576-20=556).

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic CET Superheat Calculation User ID Q2156939 System ID 2156939 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-5, Rev 03000 Steam Tables Training Objective Given a LOCA, take appropriate actions to mitigate the effects and demonstrate an understanding of the strategy, basis, and operator actions per EOP-5.

Previous NRC Exam Use None K/A Reference(s)

SF2.002.A1.13 Safety Function 2 Tier 2 Group 2 RO Imp: 3.4 SRO Imp: 4.0 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including: (CFR: 41.5 / 45.7)

Core exit thermocouples Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

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Exam Material 2021 ILT NRC RO EXAM Test Key Question 57 ID: 2161448 Points: 1.00 Which NI power indication is lost on a loss of 120VAC bus 2Y02?

A. 1C15 channel B linear range.

B. 1C43 channel B aux excore wide range.

C. Unit 2 Rx Reg Channel X.

D. 2C43 channel B aux incore wide range.

Answer B Answer Explanation A is incorrect, 1Y02 supplies Unit 1 Channel B at 1C15. Plausible if the candidate recalls that 2Y02 does power a Unit-1 Channel indication but incorrectly misinterprets the failed indication to be the 1C15 linear range instrument.

B is correct, 2Y02 supplies Channel B auxiliary Excore NIs at 1C43.

C is incorrect, Plausible since the candidate may misinterpret that 2Y02 supplies Channel X at Unit 2 Reactor Reg rather than Channel Y which is the actual Reactor Reg Channel impacted.

D is incorrect, Plausible since Channel B indications at 2C15 are supplied by 2Y01. But there are no Channel B auxiliary incores at 2C43 since only channels A and C are available.

Question Information Topic NI power indication lost due to loss of 120VAC bus 2Y02 User ID Q2161448 System ID 2161448 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

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Exam Material 2021 ILT NRC RO EXAM Test Key References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # AOP-7J-1, Rev 02400 Training Objective Predict which NI's will be lost when different power supplies are lost.

Previous NRC Exam Use NRC RO Exam - 6/2008 K/A Reference(s)

SF7.015.K6.03 Safety Function 7 Tier 2 Group 2 RO Imp: 2.6 SRO Imp: 3.0 Knowledge of the effect of a loss or malfunction on the following will have on the NIS: (CFR: 41.7 / 45.7)

Component interconnections Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

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Exam Material 2021 ILT NRC RO EXAM Test Key Question 58 ID: 2156943 Points: 1.00 When CETs are unavailable, what other criteria per EOP-2, Loss of Offsite Power, can be used to verify natural circulation?

A. T-hot minus T-cold less than 10°F B. T-hot minus T-cold less than 50°F C. T-hot minus T-cold greater than 50°F D. T-hot minus T-cold greater than 10°F Answer B Answer Explanation A. Incorrect. Plausible if the candidate misinterprets the delta T value of 10°F for verifying adequate forced circulation in place of the band for verifying natural circulation.

B. Correct. Per EOP-2, T-hot minus T-cold less than 50°F is the value used for verifying natural circulation.

C. Incorrect. Plausible if the candidate misinterprets how the relationship of delta T is used or misinterprets the value of 50°F used for adequate subcooling.

D. Incorrect. Plausible if the candidate misinterprets the delta T value and relationship or misinterprets that greater than 10°F temperature difference between T-hot and T-cold is an indication of a loss of forced circulation and verification that natural circulation is established.

Question Information Topic Identify appropriate indicators for Natural Circulation verification W/CETs unavailable User ID Q2156943 System ID 2156943 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of 10CFR55 Content temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

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Exam Material 2021 ILT NRC RO EXAM Test Key References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # EOP-2, Rev 01600 EOP-2-TB, Rev 01800 Given values for CETs and Thot, identify the relationship Training Objective between Thot and CET temperature values during the following plant conditions: Natural circulation.

Previous NRC Exam Use 2002 NRC RO K/A Reference(s)

SF7.017.K3.01 Safety Function 7 Tier 2 Group 2 RO Imp: 3.5* SRO Imp: 3.7*

Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7 / 45.6)

Natural circulation indications Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

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Exam Material 2021 ILT NRC RO EXAM Test Key Question 59 ID: 2161452 Points: 1.00 The Spent Fuel Pool system is in the following lineup:

12 SFP cooling pump - 12 SFP cooler - suction from 21 SFP and discharging to 11 SFP.

At 1000 A leak in the Spent Fuel Pool occurs concurrent with a loss of 21 4kv bus AOP-6F, SFP cooling system malfunction, is implemented AOP-7I, Loss of 4kv, 480v or 208/120v instrument bus power, is implemented Which of the following actions is required?

A. Manually stop 12 SFP pump per AOP-6F.

B. Manually stop 12 SFP pump per AOP-7I.

C. Verify 12 SFP pump automatically tripped on low SFP level.

D. Verify 12 SFP pump automatically tripped on low discharge pressure.

Answer A Answer Explanation A. Correct. Per AOP-6F, SFP pumps are manually stopped for lowering SFP level.

B. Incorrect. Plausible if the candidate recognizes that AOP-7I is implemented due to the loss of 21 4KV Bus and then incorrectly concludes that the step to secure 12 SFP is directed per AOP-7I.

C. Incorrect. Plausible if the candidate misinterprets that SFP pumps have an automatic trip on low level like the RCS drain tank pump. Per 1C13-ALM no auto trips on low level.

D. Incorrect. Plausible if the candidate misinterprets that SFP pumps have an automatic trip on low discharge pressure. Per 1C13-ALM no auto trips on low discharge pressure but this alarm would be expected for a leak on the discharge piping of the SFP pump.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Automatic operation of SFPs User ID Q2161452 System ID 2161452 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification N/A Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # 1C13-ALM, Rev 55 AOP-6F, Rev 7 Training Objective Describe the response to a loss of SFP level or cooling per AOP-6F.

Previous NRC Exam Use None K/A Reference(s)

SF8.033.K4.01 Safety Function 8 Tier 2 Group 2 RO Imp: 2.9 SRO Imp: 3.2 Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

Maintenance of spent fuel level Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

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Exam Material 2021 ILT NRC RO EXAM Test Key Question 60 ID: 2157603 Points: 1.00 Unit-1 and Unit-2 are at 100% power:

A loaded dry cask is being removed from the Spent Fuel Pool During the lift the rigging catastrophically fails, causing the cask to fall back into the SFP and come to rest on the spent fuel racks The dropped cask causes damage to the Spent Fuel Pool The Spent Fuel Pool level is lowering Which of the following describes:

(1) The most preferred source of makeup water to the SFP?

And, (2) The SFP level at which fuel would become uncovered if the damage is not fixed?

A. (1) Demineralized Water (2) 21 ft B. (1) Demineralized Water (2) 44 ft C. (1) Refueling Water Tank (2) 21 ft D. (1) Refueling Water Tank (2) 44 ft Answer D Answer Explanation A. Incorrect. (1) Plausible if the candidate misinterprets that the RWT is only for refueling pool operations and determines that DI is the preferred source at 100% power.

(2) Plausible if the candidate misinterprets the required water level above the fuel bundles vs the level where the fuel will actually become uncovered.

B. Incorrect. (1) See above. (2) Correct.

C. Incorrect. (1) Correct. (2) See above.

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Exam Material 2021 ILT NRC RO EXAM Test Key D. Correct. (1) Per AOP-6F, RWT is the preferred source of water to refill the SFP in all modes. (2) Per AOP-6F, the fuel becomes uncovered at 44 ft.

Question Information Topic Dropped Cask in the SFP User ID Q2157603 System ID 2157603 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # AOP-6D, Rev 01700 AOP-6F, Rev 00701 Training Objective Given plant conditions, diagnose a Fuel Handling Incident and respond by directing and/or implementing the proper operator actions in accordance with the procedures.

Previous NRC Exam Use None K/A Reference(s)

SF8.034.A2.02 Safety Function 8 Tier 2 Group 2 RO Imp: 3.4 SRO Imp: 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

Dropped cask Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 133 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 61 ID: 2161455 Points: 1.00 U-1 is in Mode 3 performing a reactor startup per OP-2, "Plant Startup from Hot Standby to Minimum Load". The following initial conditions exist:

Digital Feedwater Control System (DFWCS) is in AUTO Turbine Bypass Valves (TBV) in AUTO with setpoint of 900 psia ALL Reactor Trip Circuit Breakers (TCBs) are shut Crew is preparing to withdraw shutdown CEAs The reactor is manually tripped.

What impact will this have on DFWCS?

A. DFWCS will receive a signal from ESFAS AL ONLY to shift to Reactor Trip Override (RTO)

B. DFWCS will receive a signal from ESFAS BL ONLY to shift to Reactor Trip Override (RTO)

C. DFWCS will receive a signal from ESFAS AL & BL to shift to Reactor Trip Override (RTO)

D. DFWCS will remain in its present mode and continue to feed the S/Gs Answer B Answer Explanation A. Incorrect - Plausible since the operator could have the misconception that this signal comes from A logic channel or both A and B logic channels.

B. Correct - The signal to shift the DFWCS to the post trip mode uses only ESFAS B logic channel. This is activated when it receives 2 of four reactor trip bus undervoltage inputs.

C. Incorrect - Plausible since the operator could have the misconception that this signal comes from A logic channel or both A and B logic channels.

D. Incorrect - Plausible since the operator could have the misconception that you need to have a turbine trip and Rx trip bus undervoltage to get DFWCS into the post trip mode. This is plausible since this was the configuration that existed previously (Turbine trip was an input to get DFWCS into post trip mode) but is no longer the case.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic DFWCS response to TCBs opening in Mode 3 User ID Q2161455 System ID 2161455 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # AOP-7I, Rev 03400 Training Objective Given conditions and a Mode of DFWCS (Auto/Manual),

identify the proper response of the DFWCS.

Previous NRC Exam Use NRC RO Exam - 6/2008 K/A Reference(s)

SF4.035.A3.01 Safety Function 4 Tier 2 Group 2 RO Imp: 4.0 SRO Imp: 3.9 Ability to monitor automatic operation of the S/G including: (CFR: 41.7 / 45.5)

S/ G water level control Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 135 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 62 ID: 2162518 Points: 1.00 Unit-1 is in operating at 100% power:

Condenser Vacuum is lowering slowly Current Vacuum levels:

Which of the following describes:

(1) The current mode of operation of the Condenser Air Removal Units?

And, (2) Where and how will the operators verify proper operation of the CARs as the mode of operation changes on a decreasing vacuum level?

A. (1) Hogging (2) In the Control Room by mode indicating lights B. (1) Hogging (2) Locally at the CARs by valve position indications C. (1) Holding (2) In the Control Room by mode indicating lights D. (1) Holding (2) Locally at the CARs by valve position indications Test ID: 340926 02/04/2021 136 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Answer D Answer Explanation A. Incorrect. (1) Incorrect but plausible if the candidate misinterprets that since vacuum is lowering the CAR will be trying to raise vacuum by using the hogging mode. (2)

Incorrect but plausible if the candidate recalls there are various indications in the Control Room of CAR operation and vacuum levels including on the Mark VI turbine control screens, vacuum levels on 1C03, and CAR operation on 1C13.

B. Incorrect. (1) Incorrect but plausible as stated above. (2) Correct as stated below.

C. Incorrect. (1) Correct as stated below. (2) Incorrect but plausible as stated above.

D. Correct. (1) Correct per AOP-7G since the CARs are in holding mode when vacuum is greater than 25". (2) Correct since the mode change between Holding and Hogging can only be verified locally by the change in the air operated control valve positions.

Question Information Topic CAR Mode of operation User ID Q2162518 System ID 2162518 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.4 Secondary coolant and auxiliary systems that affect the facility.

References Provided Embedded Reference K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # AOP-7G-1, Rev 00400 Training Objective From memory, identify the interrelationship between the CW system and the condensate system.

Previous NRC Exam Use None Test ID: 340926 02/04/2021 137 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key K/A Reference(s)

GS.3.0.SF4.SEC.055 Safety Function 4 Tier 2 Group 2 RO Imp: SRO Imp:

Condenser Air Removal System (CARS)

P2.1.30 Safety Function 4 Tier 3 Group RO Imp: 4.4 SRO Imp: 4.0 Ability to locate and operate components, including local controls.

(CFR: 41.7 / 45.7)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

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Exam Material 2021 ILT NRC RO EXAM Test Key Question 63 ID: 2161451 Points: 1.00 Which one of the following completes the statement below concerning the Waste Gas System?

Oxygen concentration in the Waste Gas System is limited to ___(1)___ by volume per OP-CA-TRM-100 to ___(2)___.

A. (1) 20%

(2) minimize explosive gas mixture in the tank B. (1) 20%

(2) prevent internal tank corrosion C. (1) 4%

(2) prevent internal tank corrosion D. (1) 4%

(2) minimize explosive gas mixture in the tank Answer D Answer Explanation A. Incorrect. (1) See below. (2) Correct.

B. Incorrect. (1) Plausible if the candidate misinterprets that the hazardous atmosphere limit for oxygen, which is a commonly known limit in Operations to protect against hazardous conditions, is the same limit as the TRM. (2) Plausible since oxygen is a major chemical that causes corrosion in systems and is the reason why its concentration is limited in the CVCS system.

C. Incorrect. (1) Correct. (2) See above.

D. Correct. (1) Per OP-CA-TRM-100, the limit for oxygen is 4%. (2) Per OI-17B, oxygen is limited to eliminate the possibility of explosive mixtures.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Oxygen limits in waste gas and why User ID Q2161451 System ID 2161451 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.13 Procedures and equipment available for handling and disposal 10CFR55 Content of radioactive materials and effluents.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # OI-17B, Rev 02500 OP-CA-TRM-100, Rev 00700 Training Objective Operate the waste gas system in accordance with OI-17B.

Previous NRC Exam Use None K/A Reference(s)

SF9.071.K5.04 Safety Function 9 Tier 2 Group 2 RO Imp: 2.5 SRO Imp: 3.1 Knowledge of the operational implication of the following concepts as they apply to the Waste Gas Disposal System: (CFR: 41.5 / 45.7)

Relationship of hydrogen/oxygen concentrations to flammability Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 140 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 64 ID: 2160723 Points: 1.00 What automatic action is performed by the Containment High Range Radiation Monitors (RE-5317-A&B)?

A. Starts 11(21) and 12(22) Penetration Room Exhaust Fans B. Shuts the Containment Normal Sump Drain Valves, 1(2)-EAD-5462 and 5463 MOVs C. Shuts the Hydrogen Purge INBD and OUTBD ISOL MOVs, 1(2)-HP-6900 and 6901 D. Stops Containment Purge supply and exhaust fans and shuts dampers 1(2)CV-1410 and 1412 Answer C Answer Explanation A. Incorrect. Pen Room exhaust fans start on CIS. Plausible if student misinterprets the actions of CRS and CIS signals.

B. Incorrect. Containment Sump valves shut on SIAS. Plausible if student misinterprets the actions of CRS and SIAS signals.

C. Correct. Hydrogen Purge INBD and OUTBD ISOL MOVs, 1(2)-HP-6900 and 6901 shut per LD-58 isolating the auxiliary building from containment.

D. Incorrect. Containment purge secured by CRS (RI-5316A-D). Plausible if student misinterprets the actions of CRS and Containment Hi Rad.

Question Information Topic Automatic action performed by the Containment High Range Rad Monitors (RE-5317-A&B)

User ID Q2160723 System ID 2160723 Status Active Point Value 1.00 Time (min) 1 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.11 Purpose and operation of radiation monitoring systems, 10CFR55 Content including alarms and survey equipment.

Test ID: 340926 02/04/2021 141 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key References Provided None K/A Justification This question tests the knowledge of how the aux building (fuel building) is isolated from containment on an area radiation monitor high radiation signal.

SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # 1C10-ALM, Rev 05102 OI-35, Rev 04700 61058ASH0001, Rev 0055 Training Objective Identify the radiation monitors that have a control interface with another system and state their control functions.

Previous NRC Exam Use 2002 NRC K/A Reference(s)

SF7.072.K1.03 Safety Function 7 Tier 2 Group 2 RO Imp: 3.6* SRO Imp: 3.7*

Knowledge of the physical connections and/or cause- effect relationships between the ARM system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

Fuel building isolation Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 142 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 65 ID: 2161447 Points: 1.00 Unit-1 is operating at 100% power:

One Charging Pump is in operation All CVCS controllers are in AUTO Then, the following occurs:

A transient causes a change in PZR level Which one of the following describes:

If PZR level is 10 inches below setpoint, letdown flow will be _______.

A. 0 GPM B. 24 GPM C. 30 GPM D. 36 GPM Answer C Answer Explanation A. Incorrect. Plausible if the candidate misinterprets that minimum letdown flow is required to restore level and then incorrectly concludes that minimum letdown flow is 0 gpm.

B. Incorrect. Plausible if the candidate misinterprets that the HIC establishes the minimum letdown flow by subtracting RCP Bleedoff flow of 6 gpm from the minimum controller setpoint of 30 gpm to reach a total of 24 GPM. Plausible since the letdown flow setpoint generated by the controller uses a bias adjustment to match required letdown flow with the number of Charging Pumps running.

C. Correct. The HIC has a flow limiter which prevents the letdown valves from closing below 30 gpm.

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Exam Material 2021 ILT NRC RO EXAM Test Key D Incorrect. Plausible if the candidate misinterprets that the HIC establishes the minimum letdown flow by adding RCP Bleedoff flow of 6 gpm from the minimum controller setpoint of 30 gpm to reach a total of 36 GPM. Plausible since the letdown flow setpoint generated by the controller uses a bias adjustment to match required letdown flow with the number of Charging Pumps running.

Question Information Topic Interrelationship between RCS/Pzr LCS and CVCS User ID Q2161447 System ID 2161447 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # HIC-110 Calibration Data Sheet Training Objective Determine the minimum letdown flow during CVCS operation.

Previous NRC Exam Use 2012 NRC RO K/A Reference(s)

SF2.011.A4.05 Safety Function 2 Tier 2 Group 2 RO Imp: 3.2 SRO Imp: 2.9 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)

Letdown flow controller Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 144 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 66 ID: 2160736 Points: 1.00 Which of the following temporary directives can be issued and controlled by use of a STANDING ORDER?

A. Describe the preferred way of operating a system instead of an existing procedure.

B. Change the order of performance steps to a test procedure in lieu of a procedure change.

C. Require an increased monitoring plan to be utilized when remote indication of a radiation monitor is lost.

D. Provide guidance on actions to take for inoperable equipment which conflict with the Technical Specification requirements.

Answer C Answer Explanation A. Incorrect. Plausible if the candidate misinterprets that a standing order is like an operating aid and can be used to operate equipment.

B. Incorrect. Plausible if the candidate misinterprets that a standing order can direct special operations during a test based on SOS approval.

C. Correct. Per OP-AA-102-104, Standing orders are longer term, written directions from Ops management which include non-routine station operating conditions and temporary administrative requirements.

D. Incorrect. Plausible if the candidate misinterprets that a standing order can be used for inoperable equipment since the LCO would have already been entered and the TS could be conflicted with.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Temporary Management Directives User ID Q2160736 System ID 2160736 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # OP-AA-102-104, Rev 003 Training Objective Apply the requirements of OP-AA-102-104, Pertinent Information Program.

Previous NRC Exam Use Dresden 2017 RO K/A Reference(s)

P2.1.15 Safety Function 2 Tier 3 Group RO Imp: 2.7 SRO Imp: 3.4 Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.

(CFR: 41.10 / 45.12)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 146 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 67 ID: 2161063 Points: 1.00 Given:

Reactor Operator (RO) is fully qualified in the 2nd Quarter The RO ONLY works the following shifts to support OP-AA-105-102 (NRC Active License Maintenance):

6/27-Days-12 Hours-Unit 1-CRO 6/28-Nights-12 Hours-Unit 1-CRO 7/10-Days-12 Hours-Unit 1-RO 7/11-Days-12 Hours-Unit 1-RO 7/20-Nights-12 Hours-Unit 1-RO 7/25-Days-12 Hours-Unit 1-CRO Which ONE of the following completes the statements below?

Did the RO complete enough hours in the 3rd Quarter to maintain their license active, if not why?

A. Yes B. No, needed a minimum of 1 more 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> watch in June.

C. No, needed a minimum of 1 more 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> watch in July.

D. No, needed a minimum of 2 more 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> watches as the RO.

Answer C Answer Explanation A. Incorrect - Plausible if the candidate misinterprets that 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> are watch in the 3rd quarter of watch are required since this is the normal number of hours in a shift week.

B. Incorrect - Plausible if the candidate misinterprets that the 3rd quarter starts in the 6th month.

C. Correct - Per OP-AA-105-102, a licensed operator must stand at least five 12-hour shifts in a quarter to maintain their license active.

D. Incorrect - Plausible if the candidate misinterprets that only watches stood as the Test ID: 340926 02/04/2021 147 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key

'RO' count towards proficiency.

Question Information Maintaining License Proficiency per OP-AA-105-102.

Topic User ID Q2161063 System ID 2161063 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # OP-AA-105-102, Rev 15 Training Objective Apply the requirements of OP-AA-105-102, NRC Active License Maintenance.

Previous NRC Exam Use None K/A Reference(s)

P2.1.5 Safety Function 2 Tier 3 Group RO Imp: 2.9* SRO Imp: 3.9 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

(CFR: 41.10 / 43.5 / 45.12)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links Table: TRAINING-QUESTION-AN-OPS-Safety Functions 14 - Procedures Test ID: 340926 02/04/2021 148 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 68 ID: 2160824 Points: 1.00 After a Safety Related Motor Operated Valve (MOV) is opened manually (using the handwheel), what must be done to consider the MOV operable?

A. The MOV must be stroked electrically.

B. An approved Operability Determination must be made.

C. The MOV must be stroked manually in the shut direction.

D. The MOV must be viper tested per the appropriate maintenance procedure.

Answer A Answer Explanation A. Correct. Per OP-AA-103-105, Limitorque Motor-Operated and Chainwheel Operated Valve Operations, MOVs that are manually operated should be considered inoperable for remote operation until the MOV is stroked electrically to return it to the motor mode of operation.

B. Incorrect. Plausible if the candidate misinterprets that manual operation of a safety related valve impacts the valve operation and then would require an operability determination.

C. Incorrect. Plausible if the candidate misinterprets that stroking a valve manually will satisfy the technical specifications for a MOV since this does for other types of valves.

D. Incorrect. Plausible if the candidate misinterprets that using the handwheel could impact the settings of the valve which would then require a full viper testing.

Question Information Topic Manually Operated MOVs-MC User ID Q2160824 System ID 2160824 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

Test ID: 340926 02/04/2021 149 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # OP-AA-103-105, Rev 006 Training Objective Apply the requirements of OP-AA-103-105, Limitorque Motor-Operated And Chainwheel Operated Valve Operations.

Previous NRC Exam Use None K/A Reference(s)

P2.2.37 Safety Function 2 Tier 3 Group RO Imp: 3.6 SRO Imp: 4.6 Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 150 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 69 ID: 2161064 Points: 1.00 A procedure, not designated for partial performance, is being marked up to delete steps due to an equipment issue.

(1) How is placekeeping performed for the individual steps that are not going to be performed?

And, (2) Who is required to authorize the deletion of the procedure steps?

A. (1) Marked with an N/A (2) The Job Supervisor B. (1) Marked with an N/A (2) A Station Qualified Reviewer C. (1) Marked with a circle and slash (2) The Job Supervisor D. (1) Marked with a circle and slash (2) A Station Qualified Reviewer Answer B Answer Explanation A. Incorrect. Per HU-AA-104-101, a procedure that is designated for partial performance is authorized by the job supervisor and is annotated with N/As. Plausible if thought that a job supervisor can authorize the changes for any procedure even if not designated as partial performance.

B. Correct. Per HU-AA-104-101, an SQR is required to authorize partial performance for a procedure not designated as partial performance.

C. Incorrect. Plausible since the procedure still needs placekeeping and circle/slash is the normal method of placekeeping. Plausible if thought that a job supervisor can authorize the changes for any procedure even if not designated as partial performance.

D. Incorrect. Plausible since the procedure still needs placekeeping and circle/slash is the normal method of placekeeping. Plausible since the job supervisor can approve some types of partial performance.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Knowledge of partial performance of procedures User ID Q2161064 System ID 2161064 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # HU-AA-104-101, Rev 7 Training Objective Apply the requirements of HU-AA-104-101, Procedure use and Adherence.

Previous NRC Exam Use None K/A Reference(s)

P2.2.6 Safety Function 2 Tier 3 Group RO Imp: 3.0 SRO Imp: 3.6 Knowledge of the process for making changes to procedures.

(CFR: 41.10 / 43.3 / 45.13)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 152 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 70 ID: 2160828 Points: 1.00 Which of the following describes:

(1) The minimum dose rate that requires Locked High Radiation Controls (LHRA)?

And, (2) Who can issue LHRA keys?

A. (1) 100 mrem/hr (2) ONLY the Shift Manager B. (1) 100 mrem/hr (2) The Radiation Protection Manager and the Shift Manager C. (1) 1000 mrem/hr (2) ONLY the Shift Manager D. (1) 1000 mrem/hr (2) The Radiation Protection Manager and the Shift Manager Answer D Answer Explanation A. Incorrect. (1) Plausible if the candidate misinterprets the dose rate requirement for high rad vice locked high rad. (2) Plausible since the operator will recall that the Shift Manager is onsite at all times and has broad authority across multiple site processes.

B. Incorrect. (1) See above. (2) Correct.

C. Incorrect. (1) Correct. (2) See above.

D. Correct. (1) Per RP-AA-460, LHRA are when dose rates are 1000 mrem/hr. (2) Per NISP-RP-005, the RPM and the Shift Manager can issue LHRA keys.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic LHRA posting and key control User ID Q2160828 System ID 2160828 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.12 Radiological safety principles and procedures.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # RP-AA-460, Rev 37 NISP-RP-005, Rev 1 Training Objective Apply the requirements of RP-AA-460, Controls for high and locked high radiation areas.

Previous NRC Exam Use None K/A Reference(s)

P2.3.12 Safety Function 2 Tier 3 Group RO Imp: 3.2 SRO Imp: 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 45.9 / 45.10)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 154 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 71 ID: 2161066 Points: 1.00 Unit-1 is operating at 100% power:

Which of the following Area Radiation Monitors would provide automatic actions on high radiation in this condition?

(1) Containment High Range Area Rad Monitors (1-RE-5317A-B)

(2) Containment Area Rad Monitors (1-RI-5316A-D)

(3) S/G Blowdown Tank Area Rad Monitor (1-RI-7012)

A. ONLY (1)

B. ONLY (1) and (2)

C. ONLY (2) and (3)

D. (1), (2), and (3)

Answer A Answer Explanation A. Correct. Per 1C10, 1-RE-5317A&B have automatic actions that shut the purge MOVs.

B. Incorrect. Plausible if the candidate misinterprets when the 5316A-D Monitors are required. These monitors do provide automatic actions but are not in service at 100%

power.

C. Incorrect. Plausible if the candidate misinterprets when the 5316A-D Monitors are required. These monitors do provide automatic actions but are not in service at 100%

power. Plausible if the candidate misinterprets this S/G Blowdown area rad monitor with the process rad monitor for blowdown which has automatic actions. Not condition 1 is plausible if the candidate misinterprets which containment rad monitors are in service at 100% and determines that 5317A/B are not in service.

D. Incorrect. Plausible if the candidate misinterprets when the 5316A-D Monitors are required. These monitors do provide automatic actions but are not in service at 100%

power. Plausible if the candidate misinterprets this S/G Blowdown area rad monitor with the process rad monitor for blowdown which has automatic actions.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Area Radiation Monitors with Automatic actions User ID Q2161066 System ID 2161066 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.11 Purpose and operation of radiation monitoring systems, 10CFR55 Content including alarms and survey equipment.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # 1C22-ALM, Rev 04500 1C10-ALM, Rev 05102 Training Objective From memory, identify the Radiation Monitors that have a control interface with another system and recall their control functions.

Previous NRC Exam Use None K/A Reference(s)

P2.3.15 Safety Function 2 Tier 3 Group RO Imp: 2.9 SRO Imp: 3.1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.12 / 43.4 / 45.9)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 156 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 72 ID: 2160829 Points: 1.00 The Unit Supervisor is authorizing a task for an Auxiliary Building Operator to perform.

The Aux Building Operator's TEDE radiation exposure for the year is 1550 millirem.

What is the maximum dose the ABO can receive before any administrative limit is exceeded or would need to be extended?

A. 450 millirem B. 1450 millirem C. 2450 millirem D. 3450 millirem Answer A Answer Explanation A. Correct - Per RP-AA-203, the administrative dose control level is 2000 millirem cumulative TEDE per year. 2000 mr minus 1550 mr received for the year equals 450 millirem.

B. Incorrect - Plausible since the distractor of 1450 millirem would apply if the administrative dose control level was 3000 millirem. Per RP-AA-203, raising the administrative dose control level to 3000 mr is possible but requires written approval by the Radiation Protection Manager and the work group supervisor.

C. Incorrect - Plausible since the distractor of 2450 millirem would apply if the administrative dose control level was 4000 millirem. Per RP-AA-203, raising the administrative dose control level to 4000 mr is possible but requires written approval by the Radiation Protection Manager, a work group supervisor, and the Plant Manager.

D. Incorrect - Plausible since this distractor applies to the Federal/NRC Exposure Limit of 5 rem per year. Plausible since the distractor of 3450 millirem would apply if the administrative dose control level was 5000 millirem. Per RP-AA-203, raising the administrative dose control level to 5000 mr is possible but requires written approval by the Site Vice President.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Radiation control limits User ID Q2160829 System ID 2160829 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO 10CFR55 Content CFR: 41.12 Radiological safety principles and procedures.

<<NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # RP-AA-203, Rev 6 Training Objective Apply the requirements of RP-AA-203, Exposure Control and Authorization.

Previous NRC Exam Use NRC RO Exam - 12/2008 References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information K/A Reference(s)

P2.3.4 Safety Function 2 Tier 3 Group RO Imp: 3.2 SRO Imp: 3.7 Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 / 43.4 / 45.10)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 158 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 73 ID: 2161067 Points: 1.00 What does the "C" next to a block step in the Emergency Operating Procedure placekeeper mean?

A. These are steps that are continuously applicable.

B. These are steps that require concurrent verification.

C. These are steps which must be performed in sequence.

D. These are steps that Unit Supervisor may elect to never perform.

Answer A Answer Explanation A. Correct. Per OP-CA-103-102-1001, The letter C has been used for those steps that are applicable continuously or are non-sequential.

B. Incorrect. Plausible since the symbol CV is used next to steps that require concurrent verification in OIs and OPs and the candidate misinterprets that the same applies for EOPs.

C. Incorrect. Plausible if the candidate misinterprets that the C means that the steps need to be performed in sequence since the C is next to steps that are important to safety and require sustained attention.

D. Incorrect. Plausible since some steps with a C might have been already performed in EOP-0 so the US does not have to assign the block step and just mark them complete and the candidate misinterprets this to mean that the US can elect to not perform these steps.

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Exam Material 2021 ILT NRC RO EXAM Test Key Question Information Topic Knowledge of EOP symbols User ID Q2161067 System ID 2161067 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 2 Technical Reference and Revision # OP-CA-103-102-1001, Rev 008 Training Objective Apply the requirements of OP-CA-103-102-1001, Strategies For Successful Transient Mitigation.

Previous NRC Exam Use None K/A Reference(s)

P2.4.19 Safety Function 2 Tier 3 Group RO Imp: 3.4 SRO Imp: 4.1 Knowledge of EOP layout, symbols, and icons.

(CFR: 41.10 / 45.13)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 160 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 74 ID: 2115962 Points: 1.00 Which ONE of the following indicates a PAMS CET input has failed?

A. Parameter will indicate with a ?.

B. A green S adjacent to the parameter.

C. Parameter will indicate with a magenta backlight.

D. A blue backlight and a B adjacent to the parameter.

Answer C Answer Explanation A. Incorrect. Plausible since ? indicates a parameter is missing data and the operator misinterprets this to mean failed.

B. Incorrect - Plausible since a green S indicates a substituted RVLMS Probe and the candidate may misinterpret this to mean that the RVLMS probe must be failed and that is why it was substituted.

C. Correct - Per OI-1I, Post Accident Monitoring System, failed parameters will indicate with a magenta backlight.

D. Incorrect - Plausible since a "B" adjacent to the parameter indicates it is bypassed which could occur after an input was determined to be failed.

Question Information Topic PAMS indication of failed CET parameter User ID Q2115962 System ID 2115962 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.7 Design, components, and functions of control and safety 10CFR55 Content systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

NRC Exams Only Test ID: 340926 02/04/2021 161 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question Type Bank Difficulty 2 Technical Reference and Revision # OI-1I, Rev 00501 Training Objective Utilizing PAMS Flat Panel Monitor menus, displays, and functions, demonstrate proficiency in accessing and monitoring PAMS data.

Previous NRC Exam Use None References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information K/A Reference(s)

P2.4.3 Safety Function 2 Tier 3 Group RO Imp: 3.7 SRO Imp: 3.9 Ability to identify post-accident instrumentation.

(CFR: 41.6 / 45.4)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 162 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key Question 75 ID: 2161143 Points: 1.00 The following alarm is received:

The Unit Supervisor has directed the signal to be reset.

Which of the following describes:

(1) The maximum containment pressure that would allow resetting?

And, (2) The handswitches that are required to be matched to allow the signal to be reset?

A. (1) < 2.8 psig (2) All handswitches listed in the EOP Attachment B. (1) < 2.8 psig (2) ONLY the handswitches with asterisks listed in the EOP Attachment C. (1) < 4.75 psig (2) All handswitches listed in the EOP Attachment D. (1) < 4.75 psig (2) ONLY the handswitches with asterisks listed in the EOP Attachment Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

B. Correct. (1) Per 1C08-ALM, the setpoint for CIS is 2.8 psig. (2) Per EOP-ATT, only the handswitches with asterisks are required to enable CIS to be reset.

C. Incorrect (1) Plausible if the candidate misinterprets the alarm manual setpoint and the technical specification setpoint. (2) Plausible if the candidate misinterprets that all handswitches have to be matched to make sure components would not reposition after Test ID: 340926 02/04/2021 163 of 164

Exam Material 2021 ILT NRC RO EXAM Test Key the signal is reset.

D. Incorrect. (1) See above. (2) Correct.

Question Information Topic Reset CIS actions User ID Q2161143 System ID 2161143 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type RO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

References Provided None K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-ATT, Rev 02300 1C08-ALM, Rev 03700 Training Objective RECALL the terms valid, invalid, override, and reset with respect to ESFAS signals per procedures.

Previous NRC Exam Use None K/A Reference(s)

P2.4.50 Safety Function 2 Tier 3 Group RO Imp: 4.2 SRO Imp: 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

(CFR: 41.10 / 43.5 / 45.3)

Learning Objective(s)

RO NRC Test User (Sys) ID N/A (1545504)

Cross Reference Links None Test ID: 340926 02/04/2021 164 of 164

Exam Material VISION Report (Test Key) 2021 ILT NRC SRO EXAM CCNPP Operations NRC Examinations February 04, 2021 Test 2021 ILT NRC SRO EXAM VISION ID 340927 Status

NISP-TR-01 Form 7 Revision 3 Page 1 of 1 EXAMINATION COVER SHEET Exam Title (ID) 2021 ILT NRC SRO EXAM (340927)

Training Program CCNPP Operations NRC Examinations LMS Component ID Total Points 25.00 Pass Criteria = 80 %

Trainee Name Employee ID Graded By / Date Grade ____ / 25.00 = _______ %

Review and Approval Instructor Date Technical Review Date Training Supv Date Examination Rules

1. References may NOT be used during this exam, unless otherwise stated.

2. Read each question carefully before answering. If you have any questions or need clarification during the exam, contact the exam proctor.

3. Conversation with other trainees during the exam is prohibited.

4. Partial credit will NOT be considered, unless otherwise stated. Show all work and state all assumptions when partial credit may be given.

5. Restroom trips are limited and only one examinee at a time may leave.

6. For exams with time limits, you have ____ minutes to complete the exam.

7. The examinee agrees to refrain from discussing the content of the exam until the end of the exam cycle.

Examination Integrity Statement Cheating or compromising the exam will result in disciplinary actions up to and including termination.

I acknowledge that I am aware of the Exam Rules stated above. Further, I have not given, received, or observed any aid or information regarding this exam prior to or during its administration that could compromise this exam.

Examinee Signature ___________________________________________ Date ______________

Review Acknowledgement I acknowledge that the correct answers to the exam questions were indicated to me following the completion of the exam. I have had the opportunity to review the exam questions with the instructor to ensure my understanding.

Examinee Signature ___________________________________________ Date ______________

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 76 ID: 2155662 Points: 1.00

• • SRO ONLY**

Unit-1 is operating at 100% power given the following events and conditions:

A Design Basis Large Break LOCA occurs EOP-5 LOSS OF COOLANT ACCIDENT is implemented Block Step AG COMMENCE SHUTDOWN COOLING is being performed Pressurizer level is 0 inches and steady Containment spray pumps are secured CET temperatures = 275°F and steady Which one of the following statements correctly describes:

(1) What mitigation strategy is required to proceed to cold shutdown?

And (2) What is the reason why at least 3000 GPM flow must be maintained through the core at this point?

A. (1) Initiate the normal shutdown cooling alignment using OI-3B SHUTDOWN COOLING.

(2) To ensure sufficient cooling capacity to remove decay heat, minimize effects of a boron dilution event and prevent boron stratification.

B. (1) Initiate the normal shutdown cooling alignment using OI-3B SHUTDOWN COOLING.

(2) To prevent precipitation of boric acid in the reactor vessel following a break that is too large to allow the RCS to refill.

C. (1) Initiate alternate shutdown cooling per EOP-5, by aligning the LPSI pump to take suction from the containment sump and inject into the RCS with part of the flow passing through the shutdown cooling heat exchangers.

(2) To ensure sufficient cooling capacity to remove decay heat, minimize effects of a boron dilution event and prevent boron stratification.

D. (1) Initiate alternate shutdown cooling per EOP-5, by aligning the LPSI pump to take suction from the containment sump and inject into the RCS with part of the flow passing through the shutdown cooling heat exchangers.

(2) To prevent precipitation of boric acid in the reactor vessel following a break that is too large to allow the RCS to refill.

Answer C Test ID: 340927 02/04/2021 3 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Answer Explanation A. Incorrect - (1) Plausible if examinee assumes OI-3B is controlling procedure at this point not realizing DBLOCA has initiated an RAS (realigning HPSI pumps to containment sump) and Pzr level is 0 inches. For certain sized breaks (small breaks),

entry into normal shutdown cooling may be possible and can be initiated when certain plant conditions exist. When these criteria are established, Shutdown Cooling should be initiated per OI-3B, Shutdown Cooling and AOP-3B used to address any problems.

(2) correct as stated in EOP-5 Step AG basis document.

B. Incorrect - (1) Plausible as stated above. (2) Plausible if examinee confuses basis for core flush 8-11 hours after large break LOCA occurs where RCS is unable to be refilled with the basis for commencing SDC using modified SDC lineup using SIS for cold leg injection.

C. Correct - (1) per EOP-5 Basis document for Step AG page 84 - In order to use this lineup, CET temperatures must also be less than the 300°F shutdown cooling system limit, and the differential pressure between the RCS and containment must be less than 160 PSID due to LPSI pump head limitations.(2) per EOP-5 Basis document for Step AG page 84 -This requirement is based on ensuring sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F and to provide sufficient coolant circulation through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

D. Incorrect - (1) As stated above in choice C (2) Plausible as stated in B above.

Question Information Topic SRO-Alternate SDC in EOP-5 and Basis for minimum core flow User ID Q2155662 System ID 2155662 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

Test ID: 340927 02/04/2021 4 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key

<<NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # EOP-5-1 Rev 03001 Training Objective Recall the focus of operator response to various sizes of LOCAs.

Previous NRC Exam Use NRC SRO Exam - August 2006 References Provided None K/A Justification No additional information SRO-Only Justification Question requires knowledge of the major action steps for EOP-5 and the bases for these steps. This is required SRO-level knowledge.

Additional Information No additional information K/A Reference(s)

P2.1.7 Safety Function Tier 3 Group RO Imp: 4.4 SRO Imp: 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13)

GE.4.0.EPE.011 Safety Function 3 Tier 1 Group 1 RO Imp: SRO Imp:

Large Break LOCA Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 5 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 77 ID: 2161499 Points: 1.00

• • SRO ONLY**

Unit-1 is operating at 100% power when the following occurs:

An RCS leak develops inside Containment AOP-2A is implemented Which one of the following correctly completes the statements below?

Per AOP-2A, a leak on the Charging header which exceeds the capacity of the Charging Pumps can be identified by Charging header pressure indicating ___(1)___

than RCS pressure.

And, If Charging is aligned to the Aux HPSI header, and Tech Spec 3.5.2.A ECCS -

Operating is entered, the LCO required action is to restore the ECCS train to operable status within ___(2)___ hours.

A. (1) greater (2) 24 B. (1) greater (2) 72 C. (1) less (2) 24 D. (1) less (2) 72 Answer D Answer Explanation A. Incorrect. (1) Incorrect but plausible since the operator may conclude that RCS pressure will lower by a greater magnitude than Charging header pressure. The operator may also misinterpret the operation of a positive displacement pump and conclude that Charging header pressure remains constant rather than a constant flow rate. (2) Incorrect but plausible since 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is the completion time to be in Mode 5 for 3.5.3.B, ECCS - Shutdown, if the inoperable HPSI train is not restored to operable Test ID: 340927 02/04/2021 6 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key status within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time requirement.

B. Incorrect. (1) Incorrect but plausible as stated above. (2) Correct as stated below.

C. Incorrect. (1) Correct as stated below. (2) Incorrect but plausible as stated above.

D. Correct. (1) Correct since AOP-2A Section VI Block Step E contains the following note: A leak on the Charging header which exceeds the capacity of the Charging Pumps can be identified by Charging header pressure indicating less than RCS pressure. (2) Correct as stated in Tech Spec 3.5.2.A, ECCS - Operating, which has a completion time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Question Information Topic SRO-Charging Header Leak and TS Action User ID Q2161499 System ID 2161499 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO 10CFR55 Content CFR: 43.1 Conditions and limitations in the facility license.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # Tech Spec 3.5.2 Rev 326/304 Training Objective Demonstrate an understanding of the strategy and basis of AOP-2A. Determine the required actions in accordance with: Technical Specifications.

Previous NRC Exam Use None K/A Reference(s)

APE.022.AA2.02 Safety Function 2 Tier 1 Group 1 RO Imp: 3.2 SRO Imp: 3.7 Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Pump Makeup: (CFR:

43.5 / 45.13)

Charging pump problems Test ID: 340927 02/04/2021 7 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 8 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 78 ID: 2156349 Points: 1.00

• • SRO ONLY**

Unit-2 is operating at 100% power:

A spurious reactor trip occurs due to an RPS malfunction EOP-0, Post-Trip Immediate Actions is implemented All SDPS Safety Function tiles are green except for Vital Auxiliaries Vital Auxiliaries is Yellow due to Low Component Cooling System Pressure All actions possible to correct the low CC pressure have been unsuccessful Which of the following describes:

(1) The alternate action per EOP-0 required for the low CC pressure?

And, (2) After alternate actions are complete, the report for Vital Auxiliaries from the STA per the Safety Function Status Checks of EOP-0?

A. (1) Trip all RCPs (2) Complete B. (1) Trip all RCPs (2) Not Met due to no CC Flow C. (1) Shut the Component Cooling Containment Supply and Return Valves (2) Complete D. (1) Shut the Component Cooling Containment Supply and Return Valves (2) Not Met due to no CC Flow Answer A Answer Explanation A. Correct. (1) Per EOP-0, the alternate action for no CC flow is to trip the RCPs. (2)

Per EOP-0, the SFSC for Vital Auxiliaries does not look at CC.

B. Incorrect. (1) Correct. (2) See below.

C. Incorrect. (1) See below. (2) Correct.

D. Incorrect. (1) Plausible since this action is contained in AOPs to mitigate/correct Test ID: 340927 02/04/2021 9 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key abnormal CC pressures. But, incorrect since EOP-0 does not direct this action for low CC pressures. (2) Plausible if the candidate misinterprets that even after taking the required alternate actions the SFSCs are still Not met like with RLEC and Containment.

Question Information Topic SRO-Loss of CC impact on EOP-0 reports User ID Q2156349 System ID 2156349 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification SRO knowledge since the performance of the SFSCs in EOP-0 is an STA duty.

Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-00, Rev 01500 OP-CA-103-102-1001, Rev 007 Training Objective Using SPDS and the Safety Function Status Check of EOP-0, Post-Trip Immediate Actions, determine safety function status.

Previous NRC Exam Use None K/A Reference(s)

P2.1.19 Safety Function 2 Tier 3 Group RO Imp: 3.9 SRO Imp: 3.8 Ability to use plant computers to evaluate system or component status.

(CFR: 41.10 / 45.12)

GE.4.0.APE.026 Safety Function 8 Tier 1 Group 1 RO Imp: SRO Imp:

Loss of Component Cooling Water (CCW)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 10 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 79 ID: 2161502 Points: 1.00

• • SRO ONLY**

Unit-1 is operating at 100% power when the following Saltwater system indications are noted:

Which one of the following correctly describes:

(1) What is the cause of the Saltwater system indications provided?

And, (2) What actions per AOP-7A will be directed to restore Saltwater Header operability?

A. (1) Saltwater system blockage (2) Throttle open the affected Saltwater Pump miniflow valve B. (1) Saltwater system blockage (2) Throttle open the affected SRW HX Saltwater Bypass Valve C. (1) Saltwater system leakage (2) Throttle open the affected Saltwater Pump miniflow valve D. (1) Saltwater system leakage (2) Throttle open the affected SRW HX Saltwater Bypass Valve Answer B Test ID: 340927 02/04/2021 11 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Answer Explanation A. Incorrect. (1) Correct as stated below. (2) Incorrect but plausible as stated below.

B. Correct. (1) Correct as stated in 1C13 Alarm Manual Window K-31 for 12 Saltwater Flow Trouble which lists a fouled SW strainer or fouled SRW HX as possible causes.

The indications provided were created by using the malfunction of a total blockage of both 12A and 12B SRW HXs. (2) Correct per AOP-7A-1 Section V Block Step E Step 2.c which says to reduce the affected SW header pressure below the maximum SW header pressure limit by throttling open the SRW HX SW Bypass valve.

C. Incorrect. (1) Incorrect but plausible since the operator may misinterpret the indications provided to mean a SW system leakage exists. The low flow on the 12 SW header may be misinterpreted as a leak or the operator may incorrectly conclude that the lower pressure on 11 SW header is an indication of a leak on 11 SW header. (2)

Incorrect but plausible since the operator may recall that many pumps throughout the plant are protected against minimum flow conditions by installed miniflow valves. The operator will recall that opening a miniflow valve will raise system flow and lower header pressure based on known centrifugal pump laws. The operator may misinterpret the indications and conclude that a small system leakage on the flow indicating transmitter exist. Then, the operator will recall that establishing a miniflow path to ensure pump operability is required when flow indication is lost.

D. Incorrect. (1) Incorrect but plausible as stated above. (2) Correct as stated above.

The operator may misinterpret the indications and conclude that a small system leakage on the flow indicating transmitter exist. Then, the operator will recall that establishing a miniflow path to ensure pump operability is required when flow indication is lost.

Question Information Topic SRO-SW Header Blockage Indications and Actions User ID Q2161502 System ID 2161502 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided Embedded reference K/A Justification No additional information SRO-Only Justification Not applicable Additional Information No additional information NRC Exams Only Test ID: 340927 02/04/2021 12 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question Type Bank Difficulty Technical Reference and Revision # AOP-7A-1 Rev 01501 1C13 Alarm Manual Rev 05500 Training Objective Identify actions to be taken when either a rupture or system blockage occurs in the Saltwater System.

Previous NRC Exam Use None K/A Reference(s)

APE.062.AA2.02 Safety Function 4 Tier 1 Group 1 RO Imp: 2.9 SRO Imp: 3.6 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: (CFR: 43.5 /

45.13)

The cause of possible SWS loss Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 13 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 80 ID: 2155742 Points: 1.00

• • SRO ONLY**

Using provided references:

Unit-2 is operating at 100% power:

A loss of 2Y01 occurs The RICT program is not able to be applied to this failure at this time Which of the following correctly describes:

(1) The Technical Specification required completion time?

And, (2) Why?

A. (1) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (2) The level of degradation in the electrical system causes a required safety function to be lost.

B. (1) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (2) The remaining operable AC vital buses are capable of supporting the minimum safety functions necessary to shut down the unit and maintain it in the safe shutdown condition.

C. (1) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (2) The level of degradation in the electrical system causes a required safety function to be lost.

D. (1) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (2) The remaining operable AC vital buses are capable of supporting the minimum safety functions necessary to shut down the unit and maintain it in the safe shutdown condition.

Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

Test ID: 340927 02/04/2021 14 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key B. Correct. (1) Per TS 3.8.9 Basis, 2Y01 is a vital AC bus so condition B applies with a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> completion time. (2) Per the basis, with only one vital bus OOS the rest are able to support the minimum equipment needed.

C. Incorrect. (1) Plausible if the candidate misinterprets that 2Y01 is an electrical distribution bus since it supplies power to RPS, ESFAS, and AFAS cabinets. (2)

Plausible if the candidate misinterprets that since 2Y01 supplies a logic cabinet for ESFAS that a loss of half of ESFAS logic causes a safety function to be lost.

D. Incorrect. (1) See above. (2) Correct.

Question Information Topic SRO-

Reference:

TS and Basis for loss of 2Y01 User ID Q2155742 System ID 2155742 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference TS 3.8.9 Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

References Provided TS 3.8.9 K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # TS 3.8.9, Amend 304 TS Basis 3.8.9, Rev 5 Training Objective Given a set of plant conditions, correctly apply the requirements of the Tech Specs.

Previous NRC Exam Use None K/A Reference(s)

P2.1.28 Safety Function 4 Tier 3 Group RO Imp: 4.1 SRO Imp: 4.1 Knowledge of the purpose and function of major system components and controls.

(CFR: 41.7)

GE.4.0.APE.057 Safety Function 6 Tier 1 Group 1 RO Imp: SRO Imp:

Loss of Vital AC Electrical Instrument Bus Test ID: 340927 02/04/2021 15 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 16 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 81 ID: 2161737 Points: 1.00

• • SRO ONLY**

Unit-1 is operating at 100% power:

A valid reactor trip condition is received by RPS The reactor fails to trip The Reactor Operator successfully trips the reactor using the pushbuttons on 1C05 The trip path indications lights above RPS at the time of the ATWS are shown below Which of the following correctly describes:

(1) The failure of which trip path relays caused the ATWS condition?

And, (2) The correct EAL classification for the ATWS condition as described above?

A. (1) K1 and K2 Relays (2) Alert Test ID: 340927 02/04/2021 17 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key B. (1) K3 and K4 Relays (2) Alert C. (1) K3 and K4 Relays (2) Unusual Event D. (1) K1 and K2 Relays (2) Unusual Event Answer D Answer Explanation A. Incorrect. (1) Correct as stated below. (2) Incorrect but plausible since EP-AA-1011 Addendum 3 for RPS Failures states an Alert is the classification when an automatic or manual trip fails to shutdown the reactor and manual actions taken at the reactor control consoles are not successful in shutting down the reactor.

B. Incorrect. (1) Incorrect but plausible since the operator may misinterpret the indications shown above RPS. The operator may misinterpret the correct meaning of an illuminated light versus an extinguished light and will conclude that the K3 and K4 Relays are the cause of the ATWS condition. (2) Incorrect but plausible as stated above.

C. Incorrect. (1) Incorrect but plausible as stated above. (2) Correct as stated below.

D. Correct. (1) Correct as shown on the trip path indication lights above RPS. The K1 and K2 Relays are still energized, and the trip circuit breaker shunt coils and trip coils are not indicating proper actuation. This failure caused the ATWS condition that failed to trip the reactor. (2) Correct per EP-AA-1011 Addendum 3 for RPS Failures which states an Unusual Event is the classification when an automatic trip fails to shutdown the reactor and manual actions taken at the control room panels are successful in shutting down the reactor.

Test ID: 340927 02/04/2021 18 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question Information Topic SRO-

Reference:

ATWS and EAL Call User ID Q2161737 System ID 2161737 Status Active Point Value 1.00 Time (min) 4 Open or Closed Reference EP-AA-1011 Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided Embedded Reference EP-AA-1011 Addendum 3, Rev 006 K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EP-AA-1011 Addendum 3, Rev 006 Training Objective Given a set of conditions, correctly identify the EAL classification required.

Previous NRC Exam Use None K/A Reference(s)

EPE.029.EA2.07 Safety Function 1 Tier 1 Group 1 RO Imp: 4.2 SRO Imp: 4.3 Ability to determine or interpret the following as they apply to an ATWS: (CFR 43.5 / 45.13)

Reactor trip breaker indicating lights Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 19 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 82 ID: 2155828 Points: 1.00

• • SRO ONLY**

Using provided references:

Unit-2 is operating at 100% power:

At time 1000:

A Regulating CEA drops to 120" All other CEAs remain at 133.5" The CEA is still trippable Pre misalignment FrT is 1.68 What is the earliest time reactor power is required to be less than 70%?

A. 1100 B. 1200 C. 1300 D. 1400 Answer B Answer Explanation A. Incorrect. Plausible if the candidate misinterprets that value of FrT that correlates to a realignment time is 0 minutes plus the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to be at 70% power. But for a CEA misaligned by less than 15 inches FrT does not matter.

B. Correct. Per TS 3.1.4, the CEA is misaligned by 13.5 inches which allows for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to realign and then 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to be at 70% power if realignment is not completed.

C. Incorrect. Plausible if the candidate misinterprets the amount the CEA is misaligned and determines that 3.1.4.B applies which has a realignment time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> plus the one hour to be at 70% power.

D. Incorrect. Plausible if the candidate misinterprets the amount of time to realign the CEA instead of the amount of time to be at 70% power.

Test ID: 340927 02/04/2021 20 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question Information Topic SRO-

Reference:

Dropped CEA realignment time calculation User ID Q2155828 System ID 2155828 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference TS 3.1.4 Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

References Provided TS 3.1.4 K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # TS 3.1.4, Amend 201 Training Objective Given a set of plant conditions, correctly apply the requirements of the following Tech Specs: 3.1.4 CEA Alignment.

Previous NRC Exam Use None K/A Reference(s)

P2.2.22 Safety Function 1 Tier 3 Group RO Imp: 4.0 SRO Imp: 4.7 Knowledge of limiting conditions for operations and safety limits.

(CFR: 41.5 / 43.2 / 45.2)

GE.4.0.APE.003 Safety Function 1 Tier 1 Group 2 RO Imp: SRO Imp:

Dropped Control Rod Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 21 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 83 ID: 2161580 Points: 1.00

• • SRO ONLY**

Unit-1 is at 100% power and Unit-2 is in mode 5 when a fire in the control room results in a control room evacuation.

The CRO is performing the block step to verify the reactor is shutdown Which of the following describes the action that is performed and the reason why?

A. Reactor trip pushbuttons depressed at 1C43; Fire effects may have impacted the trip button circuitry in the Control Room.

B. Boration is commenced within 30 minutes from 1C43; Ensures adequate shutdown margin since CEAs cannot be credited.

C. 11 and 12 CEDM MG Sets are shutdown from the Cable Spreading Room; Ensures the CEDMs remain deenergized with power removed.

D. WRNI are isolated from the Control Room and verified less than 10-4% at 1C43; Fire effects may induce a false signal on the WRNI channels.

Answer D Answer Explanation A. Incorrect. Plausible if the candidate misinterprets what functions can be performed at 1C43 and remembers that the actions from the control room are not credited to occur and determines that the reactor must be tripped from 1C43.

B. Incorrect. Plausible if the candidate remembers the last revision of AOP-9A that required charging aligned in a certain time frame and determines those steps were to ensure the reactor was shutdown.

C. Incorrect. Plausible if the candidate remembers that the CEDMs are secured in AOP-9A as an added layer of protection to ensure the CEAs have inserted but this is not how the reactor is verified shutdown.

D. Correct. Per AOP-9A and Basis, the reactor is verified shutdown by isolating the WRNIs from the control room due to the possibility that the fire effects would cause erroneous indications.

Test ID: 340927 02/04/2021 22 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question Information Topic SRO-Confirm RX trip in AOP-9A User ID Q2161580 System ID 2161580 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # AOP-9A, Rev 01901 AOP-9A-TB, Rev 01400 Training Objective Given plant conditions, demonstrate the ability to implement the actions of AOP-9A.

Previous NRC Exam Use None K/A Reference(s)

APE.032.AA2.06 Safety Function 7 Tier 1 Group 2 RO Imp: 3.9* SRO Imp: 4.1*

Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation:

(CFR: 43.5 / 45.13)

Confirmation of reactor trip Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 23 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 84 ID: 2155903 Points: 1.00

• • SRO ONLY**

Unit-1 containment pressure is 0.4 psig A positive pressure vent is about to begin Containment High Range Radiation Monitor, 1-RI-5317A, reading is erratic, and the alarm window is OOS Which one of the following describes:

(1) The impact/mitigating strategy of removing this rad monitor from service?

And, (2) If applicable, the Tech Spec implications of this failure?

A. (1) Positive pressure vent prevented (2) No Tech Spec implications B. (1) Positive pressure vent prevented (2) 30 days to return to service per Tech Specs C. (1) Positive pressure vent allowed after verifying RI-5317B in service (2) No Tech Spec implications D. (1) Positive pressure vent allowed after verifying RI-5317B in service (2) 30 days to return to service per Tech Specs Answer D Answer Explanation A. Incorrect. (1) Plausible if the candidate misinterprets that both RMS have to be in service for the vent to happen since 2 of the CRS Containment rad monitors are required for other containment activities. (2) Plausible if the candidate misinterprets the TS requirements for the Containment particulate/gaseous radiation monitors and concludes that only 1 is required to be in service. Also, plausible if the candidate considers that other radiation monitors are covered by the ODCM and not by the Tech Specs or that some radiation monitors are not safety related equipment at all and do not have Tech Spec requirements.

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Exam Material 2021 ILT NRC SRO EXAM Test Key B. Incorrect. (1) See above. (2) Correct.

C. Incorrect. (1) Correct. (2) See above.

D. Correct. (1) Positive pressure vent Initial Conditions require ONLY one Containment High Range Rad Monitor. (2) Per TS 3.3.10, requires two Containment High Range Rad Monitor with 30 days to return.

Question Information Topic SRO-Only Containment Hi-Range RMS OOS User ID Q2155903 System ID 2155903 Status Active Point Value 1.00 Time (min) 1 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification This question pertains to information that is below the line for Technical Specifications.

Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # OI-41B, Rev 01400 Tech Spec 3.3.10, Amend 276 Training Objective Describe the response to and the condition that will indicate a system failure of the Containment Hi-Range Radiation Monitor.

Previous NRC Exam Use 2014 NRC SRO K/A Reference(s)

APE.061.AA2.06 Safety Function 7 Tier 1 Group 2 RO Imp: 3.2 SRO Imp: 4.1 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: (CFR: 43.5 / 45.13)

Required actions if alarm channel is out of service Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

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Exam Material 2021 ILT NRC SRO EXAM Test Key Cross Reference Links None Test ID: 340927 02/04/2021 26 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 85 ID: 2161655 Points: 1.00

• • SRO ONLY**

Which of the following completes the statement below:

Per EOP-8, Functional Recovery Basis, "Indication that the core is covered taken in conjunction with ___(1)___ subcooling is an indication that ___(2)___.

A. (1) 25°F (2) RCS inventory control is established B. (1) 25°F (2) sufficient shutdown margin is maintained C. (1) 30°F (2) sufficient shutdown margin is maintained D. (1) 30°F (2) RCS inventory control is established Answer A Answer Explanation A. Correct. Per EOP-8-TB, Indication that the core is covered taken in conjunction with (1) 25°F subcooling is an indication that (2) RCS inventory control is established.

B. Incorrect. (1) Correct. (2) See below.

C. Incorrect. (1) Plausible since this is the lower end of the subcooling band for many of the other optimal recovery EOPs. (2) Plausible since a lower temperature can impact shutdown margin and this impact is misinterpreted to be the reason why subcooling is maintained lower in EOP-8.

D. Incorrect. (1) See above. (2) Correct.

Test ID: 340927 02/04/2021 27 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question Information Topic SRO-Subcooling and basis in EOP-8 User ID Q2161655 System ID 2161655 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EOP-8-TB, Rev 04300 Training Objective Given situation(s) outside of the Optimum Recovery Procedures the trainee will be able to identify, understand the basis and take appropriate actions per plant operating procedures to mitigate the event(s).

Previous NRC Exam Use None K/A Reference(s)

P2.4.18 Safety Function 7 Tier 3 Group RO Imp: 3.3 SRO Imp: 4.0 Knowledge of the specific bases for EOPs.

(CFR: 41.10 / 43.1 / 45.13)

GE.4.4.E09 Safety Function 7 Tier 1 Group 2 RO Imp: SRO Imp:

Functional Recovery Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 28 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 86 ID: 2156784 Points: 1.00

• • SRO ONLY**

Unit-1 is operating at 100% power when the following occurs:

An invalid actuation of the SIAS A-5 logic module occurs The SIAS A-5 logic module shuts 1-CVC-501-MOV VCT Outlet Isolation Valve Then:

The SIAS A-5 logic module is reset 1-CVC-501-MOV VCT Outlet Isolation Valve will not reopen AOP-2B Loss of All Charging is implemented Which one of the following is the first action directed by AOP-2B if 1-CVC-501-MOV cannot be opened?

A. Establish an alternate suction flow path B. Perform a Reactor downpower using only CEAs C. Start 11 HPSI Pump aligned through the Aux HPSI header D. Verify all Charging Pump handswitches in pull to lock and Trip the Reactor Answer A Answer Explanation A. Correct. AOP-2B Section V Block Step G states that if 1-CVC-501 cannot be opened, then establish an alternate suction flow path. The step continues with the direction to use 1-CVC-504-MOV RWT Charging Pump Suction Valve, or 1-CVC-514-MOV and a Boric Acid Pump, or at least one of the BAST Gravity Feed MOVs.

B. Incorrect. Incorrect but plausible since the operator may recall the requirement to shut down the reactor if an alternate suction flow path cannot be established but may incorrectly conclude that a controlled shutdown using only CEAs would be the method used.

C. Incorrect. Incorrect but plausible since the operator may misinterpret the use of the Aux HPSI and Charging Pump flow path. A Charging Pump can be placed in service aligned to the Aux HPSI header when the normal Charging discharge flow path cannot be used. The operator may incorrectly conclude that the reverse flow path can be used Test ID: 340927 02/04/2021 29 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key in Mode 1.

D. Incorrect. Incorrect but plausible since AOP-2B Section V Block Step G Alternate Action Step 2.1 says that if an alternate suction flow path cannot be established, then verify all Charging Pump handswitches in pull to lock and trip the reactor.

Question Information Topic SRO-Invalid SIAS and AOP-2B User ID Q2156784 System ID 2156784 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-2B-1 Rev 00001 61075SH0031 Rev 0011 Training Objective From memory, describe the impact a loss of Charging has on other plant systems.

Previous NRC Exam Use None K/A Reference(s)

SF1.004.A2.12 Safety Function 1 Tier 2 Group 1 RO Imp: 4.1 SRO Imp: 4.3 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5/ 43/5 / 45/3 / 45/5)

CIAS, SIAS Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 30 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 87 ID: 2161476 Points: 1.00

• • SRO ONLY**

Using provided reference(s):

Unit-1 is at 100% power:

NO testing is in progress when an invalid CIS-B occurs CIS is reset prior to the need for a reactor trip Which of the following states reporting requirements if any are needed?

And, The reason for the requirement?

A. None, due to CIS reset.

B. A one (1) hour notification is made to the NRC, due to declaring an unusual event.

C. A four (4) hour notification is made to the NRC and within the next sixty (60) days an LER is sent, due to actuation of the reactor protection system (RPS).

D. Within the next sixty (60) days an LER is sent or phone notification is made to the NRC, due to an automatic actuation of ESFAS.

Answer D Answer Explanation A. Incorrect. Plausible if the candidate misinterprets that since the signal can be reset that no notification is required.

B. Incorrect. Plausible if the candidate misinterprets that an inadvertent ESFAS actuation is similar to an ATWS and determines a UE would be declared.

C. Incorrect. Plausible if the candidate misinterprets that CIS actuation is an RPS function and that met the criteria for RPS actuation which requires a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report.

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Exam Material 2021 ILT NRC SRO EXAM Test Key D. Correct. Per LS-AA-1020 and LS-AA-1150, a 60 day LER is required.

Question Information Topic SRO-Reference-Invalid CIS Reportability User ID Q2161476 System ID 2161476 Status Active Point Value 1.00 Time (min) 3 LS-AA-1020 Open or Closed Reference (PG5), LS-AA- Cognitive Level HIGH 1150 (PG2)

Operator Discipline LO-I Operator Type SRO CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

10CFR55 Content 10 CFR 55.43 SRO WRITTEN EXAMINATION References Provided LS-AA-1020 Page 5 LS-AA-1150 Page 2 K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # LS-AA-1020, Rev 031 LS-AA-1150, Rev 002.00 Training Objective Determine if a reportable event and/or EAL has occurred based on plant conditions.

Previous NRC Exam Use None K/A Reference(s)

SF2.013.A2.06 Safety Function 2 Tier 2 Group 1 RO Imp: 3.7* SRO Imp: 4.0 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; (CFR: 41.5 / 43.5 / 45.3 / 45.13)

Inadvertent ESFAS actuation Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 32 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 88 ID: 2156786 Points: 1.00

• • SRO ONLY**

Using provided references:

Unit-1 is operating at 100% power:

Unit-2 is shutdown with Tcold at 110°F:

A loss of 11 DC Bus occurs The actions per AOP-7J, Loss of 120V Vital AC or 125V Vital DC power, have been taken The shift manager is accessing the emergency plan for both units Which of the following describes:

(1) The EAL determination for Unit-1?

And, (2) The EAL determination for Unit-2?

A. (1) No EAL (2) No EAL B. (1) No EAL (2) Unusual Event C. (1) Unusual Event (2) Unusual Event D. (1) Unusual Event (2) No EAL Answer A Answer Explanation A. Correct. (1) Per EP-AA-1011, the event is a no call since all table M-1 parameters are able to be monitored even with the loss of 11 DC Bus. (2) Per EP-AA-1011, the event is a no call in mode 5 since only 1 bus has to be available.

B. Incorrect. (1) Correct. (2) See below.

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Exam Material 2021 ILT NRC SRO EXAM Test Key C. Incorrect. (1) Plausible if the candidate misinterprets this revision of the procedure and the last revision of the E-plan in which case this event would have been a call. (2)

Plausible if the candidate misinterprets the wording of the E-plan for the cold chart to be a UE if any of the DC buses are lost.

D. Incorrect. (1) See above. (2) Correct.

Question Information Topic SRO-

References:

Loss of DC Bus and EAL call User ID Q2156786 System ID 2156786 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference EP-AA-1011 Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided EP-AA-1011 Addendum 3 K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # EP-AA-1011 Addendum 3, Rev 006 AOP-7J, Rev 01900 Training Objective Given a set of plant conditions, and the applicable references, evaluate those conditions in accordance with EP-AA-1011.

Previous NRC Exam Use None K/A Reference(s)

GS.3.0.SF6.063 Safety Function 6 Tier 2 Group 1 RO Imp: SRO Imp:

D.C. Electrical Distribution P2.4.41 Safety Function 6 Tier 3 Group RO Imp: 2.9 SRO Imp: 4.6 Knowledge of the emergency action level thresholds and classifications.

(CFR: 41.10 / 43.5 / 45.11)

Test ID: 340927 02/04/2021 34 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 35 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 89 ID: 2161501 Points: 1.00

• • SRO ONLY**

Unit-2 is at 100% power with the following indications:

Service Water (SRW) Head Tank low level alarms Containment Normal Sump Alarm is received Both SRW Head Tanks levels are approximately 40 inches and lowering at approximately 8 inches/min The appropriate AOP is implemented Which one of the following describes:

(1) The actions required?

And, (2) The AOP basis reason for the actions performed?

A. (1) Cross-connect the SRW headers per AOP-7B.

(2) To aid the operators in determining which SRW Pump is affected and requires isolation.

B. (1) Shut Turbine Bldg SRW Isolation Valves per AOP-7B.

(2) To aid the operators in determining which SRW Pump is affected and requires isolation.

C. (1) Cross-connect the SRW headers per AOP-7B.

(2) To maintain cooling to the Non-Safety Related SRW loads.

D. (1) Shut Turbine Bldg SRW Isolation Valves per AOP-7B.

(2) To maintain cooling to the Non-Safety Related SRW loads.

Answer B Answer Explanation Test ID: 340927 02/04/2021 36 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key A. Incorrect. (1) Incorrect but plausible since this is a correct action provided for a Saltwater rupture. (2) Correct as stated below.

B. Correct - (1) Correct since indications given are rapidly lowering due to a SRW system rupture. Shutting Turbine Bldg isolations are directed per AOP-7B step V.D.2.a.

(2) Correct as stated in the AOP-7B basis document which says the action will aid the operator in determining which SRW Pump is affected.

C. Incorrect - (1) Incorrect but plausible as stated above. (2) Incorrect but plausible if the candidate recalls that this basis reason describes why SRW headers are cross connected and concludes that both SRW headers will provide cooling.

D. Incorrect - (1) Correct as stated above. (2) Incorrect but plausible if the candidate misinterprets the effect of shutting the Turbine Building SRW Isolation Valves and incorrectly concludes that cooling will be maintained to the Non Safety Related SRW components.

Question Information Topic SRO-Only Actions necessary for a leak on 21 SRW header User ID Q2161501 System ID 2161501 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty Technical Reference and Revision # AOP-7B-2 AOP-7B Technical Basis Training Objective Given a loss of Service Water, the trainee will be able to identify and understand the basis and take appropriate actions per plant operating procedures to mitigate the event.

Previous NRC Exam Use None Test ID: 340927 02/04/2021 37 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key K/A Reference(s)

GS.3.0.SF4.SEC.076 Safety Function 4 Tier 2 Group 1 RO Imp: SRO Imp:

Service Water System (SWS)

P2.1.32 Safety Function 4 Tier 3 Group RO Imp: 3.8 SRO Imp: 4.0 Ability to explain and apply system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 38 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 90 ID: 2156847 Points: 1.00

• • SRO ONLY**

Unit-1 is in Mode 6 with the following conditions:

Fuel handling is in progress in both the Spent Fuel Pool and Refueling Pool The following occurs:

All voice communications with the Main Control Room are lost In accordance with OP-7, Shutdown Operations, and the TRM, which one of the following statements is true?

A. Core Alterations may continue ONLY with specific approval of the Shift Manager.

Other irradiated fuel movement in Containment may continue without Shift manager approval.

B. All irradiated fuel movement in Containment may continue ONLY with specific approval of the Shift Manager.

C. Core Alterations must stop, other irradiated fuel movement in Containment may continue.

D. All irradiated fuel movements in Containment must stop.

Answer D Answer Explanation A. Incorrect. Plausible since permission of the Shift Manager is common for transient type conditions or a procedure deviation situation. The operator may misinterpret the TRM requirement to be only applicable to Core Alterations rather than any irradiated fuel assemblies.

B. Incorrect. Plausible since permission of the Shift Manager is a common requirement for procedure deviations or other licensed conditions.

C. Incorrect. Plausible if the operator misinterprets the TRM requirement to be only applicable to Core Alterations rather than any irradiated fuel assemblies.

D. Correct. TRM 15.9.2 is applicable during the movement of irradiated fuel in Test ID: 340927 02/04/2021 39 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Containment. If direct communications are lost, the TRM action is to suspend the movement of irradiated fuel in Containment with a restoration time of Immediately.

Question Information Topic SRO-Fuel Handling in progress and communications lost User ID Q2156847 System ID 2156847 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.6 Procedures and limitations involved in initial core loading, 10CFR55 Content alterations in core configuration, control rod programming, and determination of various internal and external effects on core reactivity.

NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # OP-7-1 Rev 05600 OP-CA-TRM-100 Rev 00700 Training Objective Given conditions for the following parameters, discriminate whether refueling may be commenced or continued in accordance with refueling procedures:

Communications.

Previous NRC Exam Use None References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information K/A Reference(s)

SF5.103.A2.02 Safety Function 5 Tier 2 Group 1 RO Imp: 2.2 SRO Imp: 3.2*

Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations (CFR: 41.5 / 43.5 / 45.3 / 45.13)

Necessary plant conditions for work in containment Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 40 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 91 ID: 2161478 Points: 1.00

• • SRO ONLY**

Unit-1 is operating at 100% power:

CEA #1 in Regulating Group 5 is noted to be out of alignment by 10 inches AOP-1B, CEA Malfunction, is implemented 2 CEAs are noted to be intermittently binding Electrical Maintenance determines the 2 intermittently binding CEAs are untrippable but moveable Which ONE of the following statements correctly describes the required actions?

A. Trip the reactor and enter EOP-0, Post Trip Immediate Actions.

B. Commence a rapid shutdown per OP-3, Normal Power Operation.

C. Maintain power at 100% and ensure all CEAs are properly aligned, per OI-42, CEDM System Operation, within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

D. Reduce power, by boration, to less than or equal to 70% per OP-3, Normal Power Operation, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Answer B Answer Explanation A. Incorrect - Plausible - A reactor trip is plausible since this is the AOP-1B trip criteria with two CEAs being misaligned by > 15.

B. Correct - This is the correct action per AOP-1B, CEA Malfunction. Tech Spec 3.1.4.F.

specifies attaining Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if one or more CEAs are untrippable or two or more CEAs are misaligned by > 15 inches. To comply with Tech Specs, AOP-1B requires a rapid down power if 2 or more CEAs are untrippable and a reactor trip if 2 or more CEAs are misaligned by > 15 inches.

C. Incorrect - Plausible - Aligning the CEAs per OI-42 is plausible since these are AOP-1B actions for a misaligned CEA and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> constitutes the total time from realignment to Tech Spec required actions.

D. Incorrect - Plausible - These actions are required for the misaligned CEA. Tech Spec 3.1.4 requires reducing power to < 70% if the required action and completion time for Test ID: 340927 02/04/2021 41 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key the misaligned CEA is not met. However, AOP-1B requires a reactor shutdown in support of the T.S. required action to be in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the untrippable CEAs.

Question Information Topic SRO-Required actions if more than one rod is stuck or inoperable User ID Q2161478 System ID 2161478 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-1B, Rev 03005 TS 3.1.4, Amend 227 Training Objective Given CEA status determine the required actions per AOP-1B and T.S.

Previous NRC Exam Use 2006 NRC SRO Exam K/A Reference(s)

SF1.014.A2.04 Safety Function 1 Tier 2 Group 2 RO Imp: 3.4 SRO Imp: 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.13)

Misaligned rod Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 42 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 92 ID: 2160729 Points: 1.00

• • SRO ONLY**

Unit-2 is operating at 100% power:

Governor Valve 1 (GV-1) fails to 100% open AOP-7E, Main Turbine Malfunction, is implemented A power reduction per the procedure is performed Repairs on GV-1 are unsuccessful Which of the following describes:

(1) The risk to the plant of having a stuck open governor valve?

And, (2) The next step in AOP-7E that the Unit Supervisor will direct?

A. (1) Overspeed protection is impaired (2) Trip the Main Turbine B. (1) Overspeed protection is impaired (2) Lower power until limited by the open governor valve and then trip the reactor C. (1) Steam header pressure could fall below the required limit per the Safety Analysis (2) Trip the Main Turbine D. (1) Steam header pressure could fall below the required limit per the Safety Analysis (2) Lower power until limited by the open governor valve and then trip the reactor Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

B. Correct. (1) Per AOP-7E-TB, if a GV is stuck open, this impairs the unit's overspeed protection. (2) Per AOP-7E, if the GV will not shut a power reduction is required until limited by the open GV and then a reactor trip is ordered.

Test ID: 340927 02/04/2021 43 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key C. Incorrect. (1) Plausible if the candidate misinterprets the basis reason for a stuck open Governor valve with the basis reason for a stuck open Throttle valve stuck open which could cause an uncontrolled RCS cooldown. (2) Plausible if the candidate misinterprets what power level is required for valve repairs and then determines that will a stuck open GV the turbine needs to be tripped for reactor safety.

D. Incorrect. (1) See above. (2) Correct.

Question Information Topic SRO-Actions for a stuck open Governor Valve User ID Q2160729 System ID 2160729 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # AOP-07E-2, Rev 01801 AOP-07E-TB, Rev 02401 Training Objective Given plant conditions, parameters, Alarm Manuals and AOP-7E, identify trip criteria, automatic and/or operator actions for the following conditions: Turbine Valve Failures.

Previous NRC Exam Use None K/A Reference(s)

SF4.045.A2.15 Safety Function 4 Tier 2 Group 2 RO Imp: 2.2* SRO Imp: 2.6*

Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.5)

Turbine overspeed Test ID: 340927 02/04/2021 44 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 45 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 93 ID: 2161479 Points: 1.00

• • SRO ONLY**

Unit 1 is operating at 100% power given the following events and conditions:

A fish kill occurs and fouls the traveling screens "Traveling Screen Diff Press Hi" Alarm occurs D/P indication in the control room on the 16A and 16B screens rises rapidly to 50 inches H20 and pegs high "Traveling Screen Shear Pin Failure" Alarm occurs The water level behind the traveling screens is (-)11 feet below the concrete surface The water level in the Chesapeake Bay is (+) 4 feet at high tide Condenser vacuum is holding steady at 26 inches Hg (1) What is the immediate danger from current plant conditions?

And (2) What are the required actions in AOP-7L Circulating Water / Intake Malfunctions to mitigate the situation?

A. (1) The traveling screens will fail at 60 inches D/P (2) Trip the 16 CW pump B. (1) The 16 CW pump will lose suction at <0 feet (2) Immediately lower the 1-SW-109/110 sluice gates on the 15/16 CW pump inlet bays C. (1) The traveling screens will fail at 60 inches D/P (2) Immediately lower the 1-SW-109/110 sluice gates on the 15/16 CW pump inlet bays D. (1) The 16 CW pump will lose suction at <0 feet (2) Trip the 16 CW pump Answer A Answer Explanation A. Correct - (1) Alarm window K-28 on 1C13 states securing CW Pp prior to > 60 inches water D/P or structural damage will occur to traveling screen (2) OI-14A Precaution D and AOP-7L directs securing a CW pump at 40 inches water.

B. Incorrect - (1) Plausible if examinee assumes water level behind traveling screens Test ID: 340927 02/04/2021 46 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key has reached trip criteria for the CW pump before it loses suction. Also, NPSH to a SW Pp may be challenged when below (-) 4 Ft. (2) Plausible if examinee does not recognize that lowering the sluice gates will have no effect on the 16 CW pump suction and will isolate inlet water sources for NPSH to 13 SW pump.

C. Incorrect - (1) Correct as stated in choice A above (2) Plausible as stated in choice B above.

D. Incorrect - (1) Plausible if examinee assumes water level behind traveling screens has reached trip criteria for the CW pump before it loses suction. Also, NPSH to a SW Pp may be challenged when below (-) 4 Ft.

Question Information Topic SRO-Given an action in AOP-7L, Fish Kill User ID Q2161479 System ID 2161479 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

<<NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # AOP-7L-1 Rev 01201 OI-14A Rev. 26 Window K-28 ALM-1C13 Rev 56 Training Objective Recognize the actions required for excessive traveling screen D/P.

Previous NRC Exam Use 2006 NRC SRO References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information K/A Reference(s)

P2.4.45 Safety Function 4 Tier 3 Group RO Imp: 4.1 SRO Imp: 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3 / 45.12)

GS.3.0.SF8.075 Safety Function 8 Tier 2 Group 2 RO Imp: SRO Imp:

Circulating Water System Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Test ID: 340927 02/04/2021 47 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Cross Reference Links None Test ID: 340927 02/04/2021 48 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 94 ID: 2160766 Points: 1.00

• • SRO ONLY**

Unit-1 is in MODE 6 with the following conditions:

Refueling Machine operations are being performed during a fuel onload with insertion of fuel assemblies into the reactor core currently in progress Maintenance personnel working on the 69 foot of Containment have asked the Fuel Handling Supervisor to perform a Supervisory Observation of their job task Which ONE of the following describes:

(1) Who can be the Fuel Handling Supervisor (FHS)?

And, (2) Whether the FHS can perform the requested observation during fuel onload?

A. (1) A Reactor Engineering Supervisor OR Senior Reactor Operator (2) The FHS can perform the observation when a fuel assembly is grappled B. (1) A Senior Reactor Operator ONLY (2) The FHS can perform the observation when a fuel assembly is grappled C. (1) A Senior Reactor Operator ONLY (2) The FHS cannot perform the observation when fuel moves are in progress D. (1) A Reactor Engineering Supervisor OR Senior Reactor Operator (2) The FHS cannot perform the observation when fuel moves are in progress Answer C Answer Explanation A. Incorrect - (1) Plausible since Reactor Engineering is directly involved with fuel moves (2) Plausible if the student misinterprets a fuel assembly being grappled to mean a fuel assembly is not being actively inserted or withdrawn from the reactor vessel allowing the observation to be performed.

B. Incorrect - (1) Correct. (2) See above.

Test ID: 340927 02/04/2021 49 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key C. Correct - (1) Per OP-CA-101-111-0200 section 4.2.3, during fuel loading, transfer or handling an FHS shall provide direct oversight. When any core component is handled in the core, the FHS shall be an SRO. (2) Per OP-CA-101-111-0200, the FHS shall directly supervise from the Containment 69 foot elevation and have no other concurrent duties.

D. Incorrect - (1) See above (2) Correct.

Question Information Topic SRO-Determine the requirements and limitations of the FHS User ID Q2160766 System ID 2160766 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO 10CFR55 Content CFR: 43.7 Fuel handling facilities and procedures.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # OP-CA-101-111-0200 Rev 002 Training Objective Determine the staffing requirements and limits of travel for the FHS.

Previous NRC Exam Use None K/A Reference(s)

P2.1.41 Safety Function 8 Tier 3 Group RO Imp: 2.8 SRO Imp: 3.7 Knowledge of the refueling process.

(CFR: 41.2 / 41.10 / 43.6 / 45.13)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 50 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 95 ID: 2161090 Points: 1.00

• • SRO ONLY**

Which of the following field activities requires direct supervision from a Senior Reactor Operator/Field Supervisor?

Condition 1 - Changing the Spent Fuel Pool System Alignment Condition 2 - ESFAS Testing at the Logic Cabinet Condition 3 - ISFSI Dry Storage Cask Loading A. Condition 1, 2 and 3 B. Condition 1 & 2 C. Condition 1 & 3 D. Condition 2 & 3 Answer B Answer Explanation Condition 1 is correct per OI-24 which states all spent fuel pool system evolutions shall be supervised by a Field Supervisor. But plausible to not require an SRO if the candidate remembers that Plant Operators can perform some evolutions in the SFP area without oversight and misinterprets that all evolutions can be performed without SRO oversight Condition 2 is correct per OI-34 which states an SRO is required for all manipulations of ESFAS cabinets. But plausible to not require an SRO if the candidate misinterprets the recent change regarding ESFAS testing philosophy that has the procedure reader as a RO instead of an SRO like in the past and determines an SRO is no longer required for ESFAS testing.

Condition 3 is incorrect but plausible if the candidate misinterprets that since ISFSI loading is moving fuel that an SRO is required but this fuel is not recently irradiated, so no SRO is required.

A. Incorrect. See above.

B. Correct. Condition 1 is correct per OI-24 which states all spent fuel pool system evolutions shall be supervised by a Field Supervisor. Condition 2 is correct per OI-34 Test ID: 340927 02/04/2021 51 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key which states an SRO is required for all manipulations of ESFAS cabinets.

C. Incorrect. See above D. Incorrect. See above.

Question Information Topic SRO-SRO oversight requirements in the field User ID Q2161090 System ID 2161090 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # OI-24A, Rev 01200 OI-34, Rev 00100 Training Objective Apply administrative procedure requirements for work controls.

Previous NRC Exam Use None K/A Reference(s)

P2.1.8 Safety Function 8 Tier 3 Group RO Imp: 3.4 SRO Imp: 4.1 Ability to coordinate personnel activities outside the control room.

(CFR: 41.10 / 45.5 / 45.12 / 45.13)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 52 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 96 ID: 2160826 Points: 1.00

• • SRO ONLY**

Given:

While rotating the idle EHC pump per the PE (Performance Evaluation), 11 EHC Pump did not start.

An IR was written, and a troubleshooting plan was prepared to troubleshoot the pump.

The maintenance crew has just arrived to begin troubleshooting.

In accordance with MA-AA-716-004, Conduct of Troubleshooting, responsibility of the Unit Supervisor is to _______.

A. complete the Failure Mode/Cause Table (FMCT) portion of the troubleshooting plan AND authorize the troubleshooting plan B. complete the Failure Mode/Cause Table (FMCT) portion of the troubleshooting plan AND lead the Complex Troubleshooting Team war room activities C. re-assess unit risk based on the troubleshooting plan AND authorize the troubleshooting plan D. re-assess unit risk based on the troubleshooting plan AND lead the Complex Troubleshooting Team war room activities Answer C Answer Explanation A. Incorrect - First part is incorrect but plausible since this is an Engineering function.

Second part is a correct responsibility of the Unit Supervisor as stated in MA-AA-716-004.

B. Incorrect - First part is incorrect but plausible since this is an Engineering function.

Second part is incorrect but plausible since this is a responsibility of the Complex Troubleshooting Team Manager as stated in MA-AA-716-004. This position would be filled by Engineering or Maintenance managers, but the candidate may misinterpret this function and conclude that the Unit Supervisor holds this responsibility.

C. Correct - Per MA-AA-716-004, Operating Shift is to evaluate the risk of each troubleshooting activity based upon plant conditions. Second part is correct since shift Test ID: 340927 02/04/2021 53 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key authorization is required to begin work as defined by the work control process.

D. Incorrect - First part is correct as stated above. Second part is incorrect but plausible as stated above.

Question Information Topic SRO-Managing troubleshooting activities User ID Q2160826 System ID 2160826 Status Active Point Value 1.00 Time (min) 2 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

<<References Provided None K/A Justification No additional information SRO-Only Justification Question asks for SRO responsibilities concerning the execution of troubleshooting Additional Information None NRC Exams Only Question Type Modified Difficulty 3 Technical Reference and Revision # MA-AA-716-004, Rev 018 Training Objective Apply the requirements of MA-AA-716-004, Conduct of Troubleshooting.

Previous NRC Exam Use None K/A Reference(s)

P2.2.20 Safety Function 8 Tier 3 Group RO Imp: 2.6 SRO Imp: 3.8 Knowledge of the process for managing troubleshooting activities.

(CFR: 41.10 / 43.5 / 45.13)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 54 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 97 ID: 2161065 Points: 1.00

• • SRO ONLY**

The plant is operating at 100% power with the following:

It is discovered that a surveillance has NOT been completed on time for a Technical Specification required system.

The surveillance frequency is 7 days.

The surveillance was last performed 11 days ago.

A risk evaluation has been performed and the associated impact is being managed.

Which one of the following describes the status of the system, in accordance with Technical Specifications?

A. The associated LCO must be declared NOT met at this time.

B. Complete the surveillance within a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from the time of discovery or then the associated LCO must be declared NOT met.

C. Complete the surveillance within a maximum of 3 days from the time of discovery or then the associated LCO must be declared NOT met.

D. Complete the surveillance within a maximum of 7 days from the time of discovery or then the associated LCO must be declared NOT met.

Answer D Answer Explanation A. Incorrect. Plausible if the SR 3.0.3 is not thought to apply to the current situation so the LCO would need to be entered immediately.

B. Incorrect. Plausible if the SR is misinterpreted to read 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or the limit of the specified frequency, whichever is shorter.

C. Incorrect. Plausible if the candidate thinks that they have an additional 7 days from the missed surveillance but this miss was 4 days ago so there are only 3 days left until you hit 7 days.

D. Correct. Surveillance Requirement (SR) 3.0.3 applies given discovery of a missed surveillance after the required frequency has elapsed. The requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the Test ID: 340927 02/04/2021 55 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key limit of the specified frequency (in this case, 7 days), whichever is greater. Therefore, up to 7 days are allowed to perform the missed surveillance before being required to declare the LCO not met.

Question Information Topic SRO-Tech Spec SR 3.0.3 requirements User ID Q2161065 System ID 2161065 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level HIGH Operator Discipline LO-I Operator Type SRO CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # Tech Spec SR 3.0.3 Given the applicable surveillance requirements, Training Objective apply the Frequency Requirements in accordance with Tech Spec Section 3.0 and the Surveillance Frequency Control Program (SFCP).

Previous NRC Exam Use None K/A Reference(s)

P2.2.38 Safety Function 8 Tier 3 Group RO Imp: 3.6 SRO Imp: 4.5 Knowledge of conditions and limitations in the facility license.

(CFR: 41.7 / 41.10 / 43.1 / 45.13)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 56 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 98 ID: 2160927 Points: 1.00

• • SRO ONLY**

A gaseous waste release is going to be performed on 13 WGDT with RI-2191 out of service. Prior to signing the waste gas permit for approval what must the Unit Supervisor verify is completed by the following groups?

(1) Chemistry?

And, (2) Operations?

A. (1) Two independent sample analyses were performed (2) An adverse condition monitoring plan is in place B. (1) Two independent sample analyses were performed (2) Two qualified Operators verified the discharge valve lineup C. (1) Two independent release flow rate calculations were performed (2) An adverse condition monitoring plan is in place D. (1) Two independent release flow rate calculations were performed (2) Two qualified Operators verified the discharge valve lineup Answer B Answer Explanation A. Incorrect. (1) Correct. (2) See below.

B. Correct. (1) Per CY-CA-170-301, with the RMS out of service, two independent samples are required. (2) Per CY-CA-170-301, with the RMS out of service, two qualified operators have to verify the discharge valve lineup.

C. Incorrect. (1) Plausible since this is an action for a discharge with the flow rate measuring device out of service and the candidate misinterprets that the RMS provides this flow rate function. (2) Plausible since an ACMP is required when many pieces of plant equipment are out of service and the candidate misinterprets that this is the required action for an RMS out of service.

D. Incorrect. (1) See above. (2) Correct.

Test ID: 340927 02/04/2021 57 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question Information Topic SRO-Actions required with 2191 OOS for a release User ID Q2160927 System ID 2160927 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type New Difficulty 3 Technical Reference and Revision # OI-35, Rev 04700 OI-17B, Rev 02500 CY-CA-170-301, Rev 3 CY-CA-170-645, Rev 0 Training Objective Determine when a Waste Gas Decay Tank can be isolated and/or released.

Previous NRC Exam Use None K/A Reference(s)

P2.3.6 Safety Function 8 Tier 3 Group RO Imp: 2.0 SRO Imp: 3.8 Ability to approve release permits.

(CFR: 41.13 / 43.4 / 45.10)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 58 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 99 ID: 2161126 Points: 1.00

• • SRO ONLY**

Which one of the following conditions would require EOP-8 implementation?

A. While performing actions of EOP-6 it is determined that both S/Gs have tube ruptures.

B. EOP-4 is being followed but the Final Safety Function Acceptance Criteria are not being met.

C. The EOP-0 flowchart recommends both EOP-4 and EOP-6 with valid rationale for each recommendation.

D. A loss of condenser vacuum results in a manual reactor trip but EOP-0 flowchart recommends consider implementing EOP-5.

Answer C Answer Explanation A. Incorrect. Plausible if the candidate determines that since you have a SGTR in each generator EOP-8 is required since you have 2 events in progress.

B. Incorrect. Plausible if the candidate misinterprets FINAL SFSC acceptance criteria with SFSC acceptance criteria since you would transition if SFSC are not met.

C. Correct. Per OP-CA-103-102-1001 and EOP-00, when the flow chart does not point to a single event diagnosis you implement EOP-8.

D. Incorrect. Plausible if the candidate misinterprets that a recommendation from the flowchart means you have that event and then determines that a loss of condenser vacuum is also an event. So, two events in progress at the same time warrants EOP-8 implementation.

Test ID: 340927 02/04/2021 59 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question Information Topic SRO-Which one of the following conditions would require EOP-8 implementation?

User ID Q2161126 System ID 2161126 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 3 Technical Reference and Revision # OP-CA-103-102-1001, Rev 008 EOP-00, Rev 01400 Training Objective Given a set of plant conditions, recall the entry process for EOP-8 in accordance with OP-CA-102-103-1001.

Previous NRC Exam Use None K/A Reference(s)

P2.4.12 Safety Function 8 Tier 3 Group RO Imp: 4.0 SRO Imp: 4.3 Knowledge of general operating crew responsibilities during emergency operations.

(CFR: 41.10 / 45.12)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 60 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key Question 100 ID: 2162520 Points: 1.00

• • SRO ONLY**

For an initial EAL Classification, what is the correct method for the Shift Manager or SRO designee to evaluate the EAL MATRIX-HOT Chart for an event?

A. Start at Unusual Event and work across to General Emergency; independent peer check by the STA is recommended.

B. Start at General Emergency and work across to Unusual Event; independent peer check by the Tech Support Center is recommended.

C. Start at Unusual Event and work across to General Emergency; independent peer check by the Tech Support Center is recommended.

D. Start at General Emergency and work across to Unusual Event; independent peer check by the STA is recommended.

Answer D Answer Explanation A. Incorrect. First part is incorrect but plausible if the candidate recalls that EP-AA-1011 does state to work across the EAL Matrix Chart in a specific order and incorrectly concludes that the order is from lowest EAL severity to the highest. The second part is correct per OP-CA-103-102-1001 which states the STA should provide a peer check of the EAL classification.

B. Incorrect. First part is correct per EP-AA-1011 which requires that all EALs be evaluated from highest (GE) to lowest (UE) EAL severity level. The second part is incorrect but plausible since the Tech Support Center provides the Control Room and the Shift Manager with technical advice and guidance during a transient event.

C. Incorrect. First part is incorrect but plausible if the candidate recalls that EP-AA-1011 does state to work across the EAL Matrix Chart in a specific order and incorrectly concludes that the order is from lowest EAL severity to the highest. The second part is incorrect but plausible since the Tech Support Center provides the Control Room and the Shift Manager with technical advice and guidance during a transient event.

D. Correct. First part is correct per EP-AA-1011 which requires that all EALs be evaluated from highest (GE) to lowest (UE) EAL severity level. The second part is correct per OP-CA-103-102-1001 which states the STA should provide a peer check of Test ID: 340927 02/04/2021 61 of 62

Exam Material 2021 ILT NRC SRO EXAM Test Key the EAL classification.

Question Information Topic SRO-EAL Classification Strategy User ID Q2162520 System ID 2162520 Status Active Point Value 1.00 Time (min) 3 Open or Closed Reference CLOSED Cognitive Level MEMORY Operator Discipline LO-I Operator Type SRO CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

<<References Provided None K/A Justification No additional information SRO-Only Justification No additional information Additional Information No additional information NRC Exams Only Question Type Bank Difficulty 2 Technical Reference and Revision # EP-AA-1011 OP-CA-103-102-1001 Rev 008 Training Objective Determine EAL Classification and Regulatory Reportability requirements to classify the event.

Previous NRC Exam Use None K/A Reference(s)

P2.4.11 Safety Function 8 Tier 3 Group RO Imp: 4.0 SRO Imp: 4.2 Knowledge of abnormal condition procedures.

(CFR: 41.10 / 43.5 / 45.13)

Learning Objective(s)

SRO NRC Test User (Sys) ID N/A (1545505)

Cross Reference Links None Test ID: 340927 02/04/2021 62 of 62