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VISION Report (Test Key) 2021 RO/SRO NRC Exam Byron ILT NRC/Cert Examination (Master)

September 15, 2021 Test 2021 RO/SRO NRC Exam VISION ID 347808 Status

NISP-TR-01 Form 7 Revision 3 Page 1 of 1 EXAMINATION COVER SHEET Exam Title (ID) 2021 RO/SRO NRC Exam (347808)

Training Program Byron ILT NRC/Cert Examination (Master)

LMS Component ID Total Points 100.00 Pass Criteria = 80 %

Trainee Name Employee ID Graded By / Date Grade ____ / 100.00 = _______ %

Review and Approval Instructor Benjamin Reyes /s/ Date 9/15/21 Technical Review Peter Leonhardt /s/ Date 9/14/21 Training Supv Brian Lewin /s/ Date 9/17/21 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 540 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 ______________

2021 RO/SRO NRC Exam Test Key Question 1 ID: 2169497 Points: 1.00

Unit 1 at 100% power.

1BOSR 3.1.5-1, TRAIN A SOLID STATE PROTECTION SYSTEM SURVEILLANCE, is in progress.

The last manipulation in 1PA09J results in the following reactor trip/bypass breaker indications at 1PM05J:

Bypass Permissive Status Light P4 RX TRIP is flashing after acknowledgment.

N41-N44 ALL indicate 5% and dropping.

ALL rod bottom lights are lit.

IR SUR is negative.

What is the NEXT procedurally required action?

A. Manually trip the reactor.

B. Go to 1BFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

C. Verify ALL turbine throttle and governor valves CLOSED.

D. Check SI status.

Answer A Answer Explanation A is Correct. Step 1 of 1BEP-0 requires that ALL conditions (rod bottom lights lit, reactor trip AND bypass breakers are OPEN, and neutron flux dropping). Although indications are that the reactor is tripped, the bypass breaker A indicates closed and the correct procedural action is to manually trip the reactor from BOTH 1PM05J and 1PM06J.

Test ID: 347808 09/15/2021 3 of 229

2021 RO/SRO NRC Exam Test Key B is Incorrect. Plausible because this is an immediate action in 1BEP-0 step one RNO column after manually tripping the reactor and power greater than 5% or IR SUR positive.

C is Incorrect. Plausible because this is the step 2 immediate action of 1BEP-0.

D is Incorrect. Plausible because this is the step 4 immediate action of 1BEP-0.

Question Information Topic 2021 NRC Q1 User ID RE10007-N02 System ID 2169497 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 1BEP-0, Rev. 304 Training Objective T.EP01-01 Previous 2 Byron NRC Exams Use None References ProvidedExam Validator Reactor Trip Breaker and Bypass Breaker diagram from 1PM01J.

K/A Justification Question meets the K/A, requires examinee knowledge of interrelations between a reactor trip and the reactor trip status panel.

SRO-Only Justification N/A Additional Information From Bwd 2018 NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

EPE.007.EK2.03 Safety Function 1 Tier 1 Group 1 RO Imp: 3.5 SRO Imp: 3.6 Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7 / 45.7)

Reactor trip status panel Test ID: 347808 09/15/2021 4 of 229

2021 RO/SRO NRC Exam Test Key Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 5 of 229

2021 RO/SRO NRC Exam Test Key Question 2 ID: 2211775 Points: 1.00

Unit 1 trip and SI were actuated from 100% power, due to a vapor space LOCA.

The crew is performing 1BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, step 6, CHECK IF ECCS FLOW SHOULD BE REDUCED.

Current plant parameters are:

Containment is 6 psig.

Subcooling is acceptable for adverse containment conditions.

RCS pressure is rising.

Pressurizer level is 15% and slowly rising.

SG levels are 32% and stable.

Total AF flow was manually throttled to 400 gpm.

With the above plant conditions ECCS flow...

A. can be reduced because ALL termination criteria are met.

B. CANNOT be reduced because SG levels are too low.

C. CANNOT be reduced because AF flow is too low.

D. CANNOT be reduced because PZR level is too low.

Answer D Answer Explanation A - Incorrect: 1BEP-1 CAS criteria for ECCS flow reduction are:

RCS subcooling acceptable (given in stem)

Secondary heat sink: Total AF flow >500 gpm OR 1 SG level >10% (31% adverse).

RCS pressure stable or rising.

Pressurizer level >12% (28% adverse).

A - Pressurizer level will not be adequate for an adverse containment. Plausible because pressurizer level is adeaquate if normal containment conditions existed.

B - Incorrect: Plausible because Unit 2 SG level is >34% for adverse containment.

C - Incorrect: Plausible because AF flow is below 500 gpm, however heat sink criteria is an OR statement (SG levels are adequate). Also, AF flow were manually reduced, therefore >500 gpm is available.

D - Correct: Per the WOG 3 Background Information for Generic Issue SI Termination/Reinitiation "The determination of whether SI can be safely terminated is focused on whether the Critical Safety Functions are satisfied and will continue to be satisfied after termination of SI. The termination of SI is accomplished in the Emergency Response Guidelines (ERGs) only after criteria symptomatic of these goals are met."

Pressurizer level criteria changes with containment conditions. Criteria for maintaining pressurizer level with adverse containment in 1BEP ES-0.1 is >28%.

Test ID: 347808 09/15/2021 6 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q2 User ID RE10008-N05 System ID 2211775 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BEP-1 Rev. 302, BACKGROUND INFORMATION FOR WESTINGHOUSE OWNERS GROUP EMERGENCY RESPONSE GUIDELINES GENERIC ISSUE SI TERMINATION/REINITIATION HP/LP-Rev. 3 Training Objective T.EP02-01-F Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the reasons (criteria) for reducing ECCS flow.

SRO-Only Justification N/A Additional Information The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

APE.008.AK3.05 Safety Function 3 Tier 1 Group 1 RO Imp: 4.0 SRO Imp: 4.5 Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: (CFR 41.5,41.10 / 45.6 / 45.13)

ECCS termination or throttling criteria Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Test ID: 347808 09/15/2021 7 of 229

2021 RO/SRO NRC Exam Test Key Cross Reference Links None Test ID: 347808 09/15/2021 8 of 229

2021 RO/SRO NRC Exam Test Key Question 3 ID: 2202657 Points: 1.00

Unit 1 is at 100% power.

An RCS LOCA and SI occur.

The crew has entered 1BEP-0, REACTOR TRIP OR SI.

If RCS pressure reaches ___1___ and SI pump discharge flow is ___2___, then the RCPs must be stopped IAW 1BEP-0.

A. 1. 1500 psig

2. 150 gpm B. 1. 1500 psig

2. 250 gpm C. 1. 350 psig

2. 150 gpm D. 1. 350 psig

2. 250 gpm Answer D Answer Explanation A - Incorrect: Plausible because there are several decision making pressure and flow setpoints in 1BEP-0 with greater than or less than criteria. This combination is the highest pressure and lowest flow.

B - Incorrect: Plausible because there are several decision making pressure and flow setpoints in 1BEP-0 with greater than or less than criteria. This combination is the highest pressure and highest flow.

C - Incorrect: Plausible because there are several decision making pressure and flow setpoints in 1BEP-0 with greater than or less than criteria. This combination is the lowest pressure and lowest flow.

D - Correct: RCS pressure is below 1425 psig which is the RCP Trip Criteria setpoint. Per 1BEP-0 OAS, the low pressure trip must be combined with >200 gpm SI pump flow.

Test ID: 347808 09/15/2021 9 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q3 User ID RE10011-N02 System ID 2202657 Status Active Point Value 1.00 Time (min) 3 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BEP-0 Rev.304 Training Objective T.EP01-05 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to operate the securing of RCPs during a large LOCA SRO-Only Justification N/A Additional Information None K/A Reference(s)

EPE.011.EA1.03 Safety Function 3 Tier 1 Group 1 RO Imp: 4.0 SRO Imp: 4.0 Ability to operate and monitor the following as they apply to a Large Break LOCA: (CFR 41.7 / 45.5 / 45.6)

Securing of RCPs Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 10 of 229

2021 RO/SRO NRC Exam Test Key Question 4 ID: 2169357 Points: 1.00

Unit 1 is in Mode 5.

1A RH pump is running in the shutdown cooling mode per BOP RH-6, OPERATION OF THE RH SYSTEM IN SHUTDOWN COOLING.

The following occurs:

Pressurizer level begins to slowly drop.

Annunciator 1-1-A2, CNMT DRAIN LEAK DETECT FLOW HIGH, alarms.

The crew enters 1BOA PRI-10, LOSS OF RH COOLING.

No other abnormal indications are present.

Which of the following possible leakage paths will the operators need to isolate to mitigate the leak?

A. A stuck open 1A RH pump Suction Relief Valve.

B. A stuck open 1A RH pump Discharge Relief Valve.

C. A body to bonnet leak of 1SI8809A, RH TO COLD LEGS 1A + 1D ISOL VLV.

D. A body to bonnet leak of 1RH8701A, RC LOOP 1A TO RH PP 1A SUCT ISOL VLV.

Answer D Answer Explanation A - Incorrect: Plausible because the suction relief is the most likely leak path for the RH system. The suction relief downstream path is hard piped to the RHUT and located outside of containment.

B - Incorrect: Plausible because the discharge relief is the second most likely leak path for the RH system. The discharge relief downstream path is hard piped to the RHUT and located outside of containment.

C - Incorrect: Plausible because the 1SI8809A valve is an outside containment isolation valve and a leak from this valve would drain into the aux bldg floor drains and the aux bldg sump.

D - Correct: The alarm 1-1-A2 has multiple inputs, however they all originate in the containment bldg.

The 1RH8701A valve is an inside containment isolation valve and a leak from this valve would drain into the containment floor drains and the reactor bldg cnmt sump.

Test ID: 347808 09/15/2021 11 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q4 User ID RE10025-N03 System ID 2169357 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BAR 1-1-A2, Rev. 10 Training Objective S.RH1-09-A Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A by requiring candidate ability to interpret rising reactor bldg sump level and using that information to determine where a loss (leak) of RH system exists.

SRO-Only Justification N/A Additional Information From Bwd 2020 NRC exam.

The question meets Tier 1 criteria because it requires assessment of plant conditions during an abnormal condition. 1BOA PRI-10 mitigation strategy is to locate and isolate the leak, then swap to the alternate RH cooling train. To complete these actions the operating crew will need to identify the leaking component in the RH system and that all inputs to alarm 1-1-A2 originate in the containment building.

K/A Reference(s)

APE.025.AA2.03 Safety Function 4 Tier 1 Group 1 RO Imp: 3.6 SRO Imp: 3.8 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: (CFR:

43.5 / 45.13)

Increasing reactor building sump level Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Test ID: 347808 09/15/2021 12 of 229

2021 RO/SRO NRC Exam Test Key Cross Reference Links None Test ID: 347808 09/15/2021 13 of 229

2021 RO/SRO NRC Exam Test Key Question 5 ID: 2169358 Points: 1.00

Unit 2 is in Mode 5.

RCS pressure is 200 psig.

2A CV pump is in operation.

VCT pressure is 15 psig.

U-0 CC Pump and HX are mechanically aligned to Unit 2.

2A RH pump is running in the shutdown cooling mode.

Unit 2 FC cooling loop is in operation.

The following MCR indications are noted:

Annunciator 2-2-A5, CC SURGE TANK LEVEL HIGH LOW, alarms.

CC Surge Tank level indication is 65% and slowly RISING.

0PR09J and 2PR09J Rad Monitors are at ALERT alarm and rising.

The crew entered 2BOA PRI-6, COMPONENT COOLING MALFUNCTION, and is currently performing ATTACHMENT B, step 6, ISOLATE CC INLEAKAGE.

Which one of the following heat exchangers will the crew isolate to mitigate the leak?

A. 2A RH Hx B. U-2 FC Hx C. U-0 CC Hx D. U-2 Seal Water Hx Answer A Answer Explanation A is correct, 2BOA PRI-6, attachment B, lists sources of CC inleakage and outleakage. With CC surge tank level rising the only choice which would cause CC inleakage is the online RH HX. CC system pressure is typically 130-140 psig at the CC pump discharge and slightly lower at the system loads (depending on flow and system head loses). RH system pressure at the RH Hx is approx. 260 psig. The RH pump head will add about 160# to suction pressure (RCS pressure) at normal flow. Therefore, rising CC surge tank level would indicate an RH Hx leak.

B is incorrect, Plausible because FC Hx is listed as potential source of CC outleakage per 2BOA PRI-6.

FC pressure is normally 50-90 psig (lower than CC pressure).

C is incorrect, Plausible because U-0 CC Hx is listed as potential source of CC outleakage per 2BOA PRI-6. SX pressure is normally 80-110 psig (lower than CC pressure).

D is incorrect, Plausible because seal water Hx is listed as potential source of CC outleakage per 2BOA PRI-6. Seal return pressure is determined by backpressure of VCT. At 15 psig VCT pressure, seal return pressure will be lower than CC pressure.

Test ID: 347808 09/15/2021 14 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q5 User ID RE10025-N01 System ID 2169358 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 2BOA PRI-6, Rev. 114 Training Objective T.OA17-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to recognize abnormal indications for CC system operating parameters that are entry level for 2BOA PRI-6.

SRO-Only Justification N/A Additional Information From Bwd 2009 NRC exam.

The question meets Tier 1 criteria because it requires assessment of plant conditions during an abnormal condition. 2BOA PRI-6 mitigation strategy is to locate and isolate the system in leakage. To complete these actions the operating crew will need to identify the leaking component.

K/A Reference(s)

P2.4.4 Safety Function 4 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.APE.026 Safety Function 8 Tier 1 Group 1 RO Imp: SRO Imp:

Loss of Component Cooling Water (CCW)

Test ID: 347808 09/15/2021 15 of 229

2021 RO/SRO NRC Exam Test Key Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 16 of 229

2021 RO/SRO NRC Exam Test Key Question 6 ID: 2202680 Points: 1.00

Unit 1 is in Mode 3 at NOP/NOT.

Pressurizer pressure control is in AUTOMATIC.

PZR pressure channel 1PT-457 is in TEST (all required bistables tripped).

Subsequently the following occurs:

1PT-458 fails LOW.

SI ACTUATES and all equipment functions as designed.

5 minutes later, NO manual operator actions have been taken and the following conditions are noted:

Tave is 555°F and slowly LOWERING.

Pressurizer level is 35% and slowly RISING.

Pressurizer pressure is 2280 psig and slowly RISING.

1PK-0455A, MASTER PZR PRESS CONT, demand is 50%.

With the above conditions, PZR Backup Heaters will be ___1___ and PZR spray valves will be ___2___.

A. 1. Off

2. Closed B. 1. Off

2. Open C. 1. On

2. Closed D. 1. On

2. Open Answer C Answer Explanation A is incorrect, heaters are on because of the pressurizer level deviation from program. Plausible because pressurizer pressure is high.

B is incorrect, opposite from correct answer. Plausible because pressurizer pressure is high which normally would turn heaters off and spray valves open.

C is correct, When SI actuates from Mode 3, NOP/NOT conditions, RCS temp will drop slowly due to the injection of ECCS flow and pressure will rise slowly due to the pressurizer bubble being compressed by an insurge. The pressurizer insurge of relatively cooler water (if allowed to continue long term) may have the effect of losing saturation conditions in the pressurizer. The PZR backup heaters are interlocked to turn on when PZR level reaches or exceeds 5% above program level. In this condition, program level will initially be at minimum (25%). Therefore, the backup heaters will be on with PZR level at 35%. Actual PZR pressure and master pressure controller demand will not demand heaters to be on and will demand PZR spray valves to be open. However, the 5% above program level interlock will override the heater Test ID: 347808 09/15/2021 17 of 229

2021 RO/SRO NRC Exam Test Key demand and turn on the backup heaters. PZR sprays will not be open because the SI will cause a containment phase A isolation and isolate instrument air to containment failing the PZR spray valves closed.

D is incorrect, spray valves are closed due to loss of instrument air to containment. Plausible because pressurizer pressure is high.

Question Information Topic 2021 NRC Q6 User ID RE10027-N04 System ID 2202680 Status Active Point Value 1.00 Time (min) 1 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BAR 1-12-C3 Rev. 4 Training Objective T.OA11-25 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to know the operational implications of a potential loss of saturation conditions in the pressurizer. Backup heaters are energized during pressurizer insurge conditions to add latent heat of vaporization and maintain saturation conditions.

SRO-Only Justification N/A Additional Information From Bwd 2016 NRC exam.

The question meets Tier 1 criteria because it requires assessment of the integrated plant response to emergency or abnormal situations crossing several plant systems and/or safety functions. This question tests applicants knowledge of the response of the pressurizer pressure control and ESF systems during an abnormal situation.

Test ID: 347808 09/15/2021 18 of 229

2021 RO/SRO NRC Exam Test Key K/A Reference(s)

APE.027.AK1.03 Safety Function 3 Tier 1 Group 1 RO Imp: 2.6 SRO Imp: 2.9 Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions: (CFR 41.8 / 41.10 / 45.3)

Latent heat of vaporization/condensation Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 19 of 229

2021 RO/SRO NRC Exam Test Key Question 7 ID: 2169361 Points: 1.00

Unit 1 has experienced an ATWS event.

The crew is performing 1BFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

An EO is dispatched to locally perform step 6.a, LOCALLY PERFORM THE FOLLOWING UNTIL THE REACTOR IS TRIPPED.

BOTH U-1 Reactor Trip Breakers FAIL to open locally.

IF the EO performed the following actions in the listed order, by placing the associated control switch in PULL OUT, WHEN would the reactor trip?:

1. OPENS the 1A MG SET GENERATOR Breaker.

2. OPENS the 1B MG SET GENERATOR Breaker.

3. OPENS the 1A MG SET MOTOR Breaker.

4. OPENS the 1B MG SET MOTOR Breaker.

A. Action 1 B. Action 2 C. Action 3 D. Action 4 Answer B Answer Explanation A is incorrect, power is still available from the 1B MG set.

B is correct, 1BFR S-1 step 6 RNO has the operator locally perform actions "until the reactor is tripped".

The MG sets providing power to the reactor trip breakers are arranged in parallel and then cross tied at the generator output before feeding in series trip breakers. Either MG set provides enough power to maintain the rod control system energized. Therefore, power will not be interrupted to the rod drive power cabinets until at least one generator or one motor breaker is open from both trains of MG sets.

C is incorrect, reactor trip occurred at previous step.

D is incorrect, reactor trip occurred at step 2.

Test ID: 347808 09/15/2021 20 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q7 User ID RE10029-N02 System ID 2169361 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 1BFR S.1, Rev. 303 Training Objective 3D.FR-01-B Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the interrelationship between breakers in the rod drive power system and an ATWS condition.

SRO-Only Justification N/A Additional Information From Bwd 2011 NRC exam.

The question meets Tier 1 criteria because it requires assessment of the integrated plant response to emergency or abnormal situations crossing several plant systems and/or safety functions. This question tests applicants knowledge of the response of the AC electrical distribution and the rod drive systems during an emergency situation. The question also tests the applicants knowledge of the progression of the event as the procedure steps are performed.

K/A Reference(s)

EPE.029.EK2.06 Safety Function 1 Tier 1 Group 1 RO Imp: 2.9* SRO Imp: 3.1*

Knowledge of the interrelations between the and the following an ATWS: (CFR 41.7 / 45.7)

Breakers, relays, and disconnects Test ID: 347808 09/15/2021 21 of 229

2021 RO/SRO NRC Exam Test Key Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 22 of 229

2021 RO/SRO NRC Exam Test Key Question 8 ID: 2169362 Points: 1.00 During a design basis Steam Generator Tube Rupture (SGTR) event, operators are required to isolate Auxiliary Feed Water (AFW) flow to the affected SG within a specified amount of time.

What is the reason for closing the AF isolation and throttle valves to a ruptured S/G IAW 1BEP-3, STEAM GENERATOR TUBE RUPTURE?

A. Conserve CST inventory.

B. Promote SG thermal stratification.

C. Minimize the probability of SG overfill.

D. Limit the cooling effect so SG pressure remains high.

Answer C Answer Explanation A - Incorrect: CST inventory is not the concern for isolating AF during a SGTR. Plausible because the TS basis for CST level requirement has a time limit for initiating an RCS cooldown to place the plant on RH cooling.

B - Incorrect: Plausible because maintaining SG thermal stratification is the basis for minimum level to be maintained in the ruptured SG. Per the Design Basis of EP-3, EOP Step 4 checks for ruptured SG Level.

This is done to establish and maintain a water level in the ruptured steam generators above the U-tubes in order to promote thermal stratification to prevent ruptured steam generator depressurization. It is important to maintain level above the U-tubes to prevent them from coming in contact with the steam space. This ensures, that when the primary is cooled, the steam space does not cool which would cause a drop in pressure and allow more primary to secondary leakage.

C - Correct: Per BD-EP-3, the purpose of step 4b., closing ruptured SG AF isolation valves, is to minimize the potential for SG overfill.

D - Incorrect: Plausible because maintaining SG pressure high facilitates a normal (per 1BEP-3) RCS cooldown. Whereas, low ruptured SG pressure would require a transition to 1BCA-3.1 and a more complicated plant recovery.

Test ID: 347808 09/15/2021 23 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q8 User ID BW-COPS1-011 System ID 2169362 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # BD-EP-3, Rev. 300 Training Objective T.EP04-01 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to know reason for isolating AF to a ruptured SG during a SGTR event.

SRO-Only Justification N/A Additional Information From Bwd COPS exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

EPE.038.EK3.06 Safety Function 3 Tier 1 Group 1 RO Imp: 4.2 SRO Imp: 4.5 Knowledge of the reasons for the following responses as the apply to the SGTR: (CFR 41.5 / 41.10 / 45.6 / 45.13)

Actions contained in EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 24 of 229

2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 25 of 229

2021 RO/SRO NRC Exam Test Key Question 9 ID: 2169363 Points: 1.00

Unit 1 was at 100% power.

The crew observed the following indications:

All steam generator pressures LOWERING

Tave LOWERING

Reactor power RISING The following sequence of events occur:

Time = 0 sec. - A manual reactor trip is initiated.

Time = 3 sec. - A manual SI is initiated.

Time = 11 sec. - Tave drops to 564°F.

Time = 17 sec. - Tave drops to 550°F.

When in the time sequence did feedwater isolation actuate?

A. Time = 0 sec.

B. Time = 3 sec.

C. Time = 11 sec.

D. Time = 17 sec.

Answer B Answer Explanation A - Incorrect: Plausible because a manual reactor trip signal is half of (one of) the FWI auto actuations coincidences combined with Lo Tave of 564°F. The original plant design was FWI actuated solely with a P-4 (reactor trip) signal. A plant modification changed the FWI actuation a 2/2 coincidence.

B - Correct: Auto FWI signals are:

P-4 combined with Low Tave

SI

P-14 The SI actuation would preempt the P-4/Low Tave signal and actuate FWI.

C - Incorrect: The SI actuation would preempt the P-4/Low Tave signal and actuate FWI. Plausible because Low Tave of 564°F combined with a manual reactor trip signal is one of the FWI auto actuation signals.

D - Incorrect: Plausible because 550°F is the Low-2 Tave signal that actuates the steam dump closure.

Test ID: 347808 09/15/2021 26 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q9 User ID RE10040-N04 System ID 2169363 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # BAR 1-15-E7, Rev 4 Training Objective S.EF1-07-C Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor for FWI during a steam line rupture event.

SRO-Only Justification N/A Additional Information The question meets Tier 1 criteria because it requires assessment of the progression of an emergency situation and assessment of the integrated plant response to emergency or abnormal situations crossing several plant systems and/or safety functions. This question tests an applicants knowledge of the response of the RCS and ESF systems during an emergency situation.

K/A Reference(s)

APE.040.AA1.02 Safety Function 4 Tier 1 Group 1 RO Imp: 4.5 SRO Imp: 4.5 Ability to operate and / or monitor the following as they apply to the Steam Line Rupture: (CFR 41.7 / 45.5 / 45.6)

Feedwater isolation Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 27 of 229

2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 28 of 229

2021 RO/SRO NRC Exam Test Key Question 10 ID: 2202130 Points: 1.00 Which of the following plant power levels and FW pump trips would require an IMMEDIATE manual reactor trip per 1BOA SEC-1, SECONDARY PUMP TRIP?

Condition 1. 14% power with ONLY the 1B FW pump running, and the 1B FW pump TRIPS.

Condition 2. 75% power with BOTH the 1A and 1B FW pumps running, and the 1B FW pump TRIPS.

Condition 3. 75% power with BOTH the 1A and 1B FW pumps running, and BOTH the 1A and 1B FW pumps TRIP concurrently.

A. Condition 1 ONLY B. Conditions 1 AND 3 C. Conditions 2 AND 3 D. Condition 3 ONLY Answer D Answer Explanation A - Incorrect: 1BOA SEC-1, Attachment A will attempt a fast start of the 1A FW pump to restore FW flow in this condition. Although the auto start function of the 1A FW pump will be blocked below 58% power, the manual fast start function is still available. Plausible because a reactor trip at lower power levels is a less severe plant transient than a trip from higher power levels. Also, several procedures have a lower threshold for tripping the reactor (due to transients) at lower power levels.

Examples include:

1BOA SEC-3. LOSS OF CONDENSER VACUUM, where the threshold for tripping is lower (less condenser pressure rise) at lower power levels.

1BOA ROD-3, DROPPED OR MISALIGNED ROD, where the reactor is immediately tripped when <5%

power vs, allowing rod recovery at higher power levels.

B - Incorrect: Plausible because both conditions are a loss of all FW flow. See above explanation for Condition 1 distractor.

C - Incorrect: Plausible because both conditions are greater than 700MW. However, for condition 2, 1BOA SEC-1 will direct a turbine runback to < 700 MW which is within the capabilities of a single FW pump.

D - Correct: Per 1BOA SEC-1 OAS, IF >700 MW with NO FW Pumps Running: Trip the Reactor and GO TO 1BEP-0. 700 MW is approximately 55% reactor power, therefore a loss of both running FW pumps at 75% power requires an immediate manual reactor trip.

Test ID: 347808 09/15/2021 29 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q10 User ID RE10054-N06 System ID 2202130 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BOA SEC-1, Rev. 114 Training Objective S.CD1-06-C Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to interpret the loss of all FW flow vs. the trip of one FW pump.

SRO-Only Justification N/A Additional Information The question meets Tier 1 criteria because it requires assessment of plant conditions during an abnormal condition and determine when a reactor trip is required per 1BOA SEC-1.

K/A Reference(s)

APE.054.AA2.02 Safety Function 4 Tier 1 Group 1 RO Imp: 4.1 SRO Imp: 4.4 Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): (CFR: 43.5 /

45.13)

Differentiation between loss of all MFW and trip of one MFW pump Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 30 of 229

2021 RO/SRO NRC Exam Test Key Question 11 ID: 2169563 Points: 1.00

The crew is performing 1BCA-0.0, LOSS OF ALL AC POWER, Attachment B, EXTENDED LOSS OF ALL AC POWER RESPONSE.

EOs are performing Step 10, DEPRESSURIZE ALL INTACT SGs TO 260 PSIG.

What is the bases for depressurizing the SGs?

A. Minimize RCS inventory loss through the RCP seals.

B. Maximize Aux. Feed flow rates.

C. Enhance natural circulation of the RCS.

D. Minimize S/G tube differential pressure.

Answer A Answer Explanation A - Correct: Minimize RCS inventory loss is correct. Per the WOG background document for CA-0.0, the basis for depressurizing the SGs is to reduce RCS temperature and pressure to reduce RCP seal leakage and minimize RCS inventory loss. Per the ERG background document for ECA-0.0, operator action is taken to reduce SG pressures prior to allowing them to reach the SG safety setpoints to minimize the RCS inventory loss from imminent RCP seal failure. All RCPs have been modified with the Westinghouse SHIELD Passive Thermal Shutdown Seal system (SDS). Developed to restrict RCS inventory losses to very low leak rate when plant event causes loss of all RCP seal cooling. However, some leakage will still occur during an extended loss of all AC power. Therefore the procedure steps and bases to depressurize the SG to 260 psig are still applicable.

B - Plausible: Maximize Aux. Feed flow rates is incorrect. The 1B AF pump is designed with adequate pump head pressure (990 gpm at 1450 psig) to overcome SG pressures up to the SG safety setpoints, therefore there is no reason to depressurize to raise flow. The examinee may plausibly conclude pressure is lowered to fill the S/Gs like BEP-3 where the RCS is depressurized to refill the PZR.

C - Plausible: Enhancing natural circulation is incorrect. Dumping steam in 1BEP ES-0.2 is a strategy to perform a controlled cooldown of the RCS and enhance natural circulationt, making this distractor plausible. However, this strategy is to maintain a cooldown rate of less than 50°F/hour and is more conservative than the dumping of steam in 1BCA-0.0.

D - Plausible: Minimize S/G tube differential pressure is incorrect. During a SGTR event, steam is dumped to cooldown and eventually depressurize the RCS, however S/G tube DP is not a primary concern during an loss of all AC event since the RCS pressure will be dropping due to the seal leakage.

The examinee may plausibly conclude RCS pressure has lowered below S/G Pressure, due to the potential for an RCS LOCA through the RCP seals, and the DP must be reduced. The design limit for DP across the SG tubes is 1600 psid primary to secondary, and 670 psid secondary to primary.

Test ID: 347808 09/15/2021 31 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q11 User ID RE10055-G2.4.6-11 System ID 2169563 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BD-CA-0.0, Rev. 300 Training Objective T.CA1-06 Previous 2 Byron NRC Exam Use None References Provided None K/A Justification This question meets the KA because the examinee must have a knowledge of the operational affects of local operator action of depressurizing the SGs.

SRO-Only Justification Not applicable Additional Information From 2019 Bwd NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

P2.4.35 Safety Function 4 Tier 3 Group RO Imp: 3.8 SRO Imp: 4.0 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13)

GE.4.0.EPE.055 Safety Function 6 Tier 1 Group 1 RO Imp: SRO Imp:

Loss of Offsite and Onsite Power (Station Blackout)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 32 of 229

2021 RO/SRO NRC Exam Test Key Question 12 ID: 2169366 Points: 1.00

Unit 1 experienced a reactor trip from full power.

One minute later, a loss of offsite power occurred.

Currently (90 minutes after the loss of offsite power):

The crew is implementing 1BEP ES-0.2, NATURAL CIRCULATION COOLDOWN.

RCS pressure is 885 PSIG.

ALL SG pressures are 763 PSIG.

CETCs indicate 532oF.

RCS cold leg temperatures indicate 515.5oF .

SATURATED conditions are indicated in the ___1___ .

In response, operators will ____2____.

A. 1. reactor vessel plenum

2. actuate safety injection B. 1. SG tubes

2. limit the RCS cooldown rate to 11oF/hour C. 1. reactor vessel plenum

2. limit the RCS cooldown rate to 11oF/hour D. 1. SG tubes

2. actuate safety injection Answer A Answer Explanation A is Correct: Saturation temperature for 885 psig (900 psia) is 532oF. CETCs measure fluid temperature of the plenum, therefore the CETCs at 532oF is a direct indication of plenum saturation. A cold leg temperature of at 515oF means the cold leg is at the saturation temperature for the secondary pressure of the SGs (515oF is the saturation temperature for 778 psia or 763 psig) and is one of the indications used to determine that natural circulation is occurring (per Attachment B of 1BEP ES-0.1, REACTOR TRIP RESPONSE). 1BEP ES-0.2 OAS directs operators to actuate SI and go to 1BEP-0, REACTOR TRIP OR SAFETY INJECTION, if RCS subcooling is unacceptable. With the plenum at saturated conditions, there is no subcooling (i.e. unacceptable) so the criteria is met to acuate SI.

B is Incorrect: Part 1 is plausible because the candidate may calculate saturation conditions in the SG tubes using the given secondary SG pressure. Part 2 is plausible because 1BEP ES-0.2 Step 7.c RNO directs step to reduce the cooldown rate to 11oF to address the development of a stagnant loop. This is also contained in the CAS for to respond to the development of an inactive RCS loop or stagnant loop is indicated.

C is Incorrect: See plausibility explanation in distractor B.

D is Incorrect: See plausibility explanation in distractor B.

Test ID: 347808 09/15/2021 33 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q12 User ID RE10056-C02 System ID 2169366 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # Steam tables. 1BEP ES-0.2, Rev. 302 Training Objective T.EP01-05 Previous 2 Byron NRC Exams Use None References Provided Steam tables.

K/A Justification Question meets the K/A, requires examinee to determine the correct indication for saturation in the plenum and determine the correct operational response.

SRO-Only Justification N/A Additional Information From Bwd 2013 NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

APE.056.AK1.04 Safety Function 6 Tier 1 Group 1 RO Imp: 3.1* SRO Imp: 3.2*

Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: CFR 41.8 / 41.10 / 45.3)

Definition of saturation conditions, implication for the systems Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Test ID: 347808 09/15/2021 34 of 229

2021 RO/SRO NRC Exam Test Key Cross Reference Links None Test ID: 347808 09/15/2021 35 of 229

2021 RO/SRO NRC Exam Test Key Question 13 ID: 2169367 Points: 1.00

An RCS LOCA occurred on Unit 1 from 100% power.

A simultaneous loss of an AC Instrument Bus results in A train of ESF pumps failing to start automatically.

An NSO is performing 1BEP-0, REACTOR TRIP OR SI, ATTACHMENT B, SI VERIFICATION.

When the NSO is performing step 10, CHECK IF CS IS REQUIRED, containment pressure is above the CS actuation setpoint.

The 1B CS pump is RUNNING In 1BEP-0, will the 1A CS pump be started?

The 1A CS pump...

A. WILL be started in a separate 1BEP-0 attachment regardless of current plant conditions.

B. WILL be started in a separate 1BEP-0 attachment if the number of RCFCs operating is inadequate.

C. would NOT be started in 1BEP-0 because the instrument bus loss prevents a manual start.

D. would NOT be started in 1BEP-0 because 1 CS pump is adequate to mitigate plant conditions.

Answer D Answer Explanation A - Incorrect: Although 1BEP-0, Attachment directs manual starting of CS pumps, it does not check if any RCFCs are operating. Plausible because all other ECCS pumps are manually started in 1BEP-0 regardless of the status of the opposite train pump or equipment.

B - Incorrect: Although 1BEP-0, Attachment directs manual starting of CS pumps, it does not check if any RCFCs are operating. Plausible because 1BEP-1, step 7 assesses whether CS pumps should be shut down based upon containment pressure and number of RCFCs operating.

C - Incorrect: Attachment B, step 10 does not manually start the CS pump. The step directs manual actuation of the CS / Phase B control switches. The switches will fail to function due to the loss of the instrument bus. The RNO of the step is satisified with a single train of CS in operation. In order to manual start the CS pump, several actions are required in order to meet the starting interlocks for a manual pump start and are specified in 1BEP-0 Attachment C and are beyond the scope for simple operator action. Plausible because all other ESF pumps are manually started in the associated RNO column of attachment B.

D - Correct: Per 1BEP-0, step 10 (part of CAS), the NSO will only transition to attachment C if there are NO CS pumps operating.

Test ID: 347808 09/15/2021 36 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q13 User ID RE10057-N02 System ID 2169367 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BEP-0, Rev. 304 Training Objective T.EP01-05 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to determine actions in EOP that are the result of a loss of a vital AC instrument bus.

SRO-Only Justification N/A Additional Information The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

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) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 37 of 229

2021 RO/SRO NRC Exam Test Key Question 14 ID: 2169368 Points: 1.00

Unit 1 is recovering from a SX leak resulting in a large section of the SX system being isolated.

In response to the change in system configuration, the crew must throttle 1SX007, CC HX OUTLET VLV, while monitoring CC HX Outlet Temperature.

Where will each task be accomplished?

1. Throttle 1SX007...

2. Monitor 1TI-674, CC HX Outlet Temp...

A. 1. in the MCR.

2. locally in the plant.

B. 1. in the MCR.

2. in the MCR.

C. 1. locally in the plant.

2. in the MCR.

D. 1. locally in the plant.

2. locally in the plant.

Answer C Answer Explanation A - Plausible: There are evolutions where valves are throttled from the MCR while local observation of flow and/or temperatures is required.

B - Plausible: There are evolutions where valves are throttled from the MCR while MCR observation of flow and/or temperatures is required.

C - Correct: 1SX007 is a locally controlled valve operated by a hand switch mounted in local proximity to the valve on 346' elevation in the aux bldg. The CC HX Outlet temperature is in the MCR on 1TI-674 mounted on 1PM06J panel and on the DCS Ovation CC Hx graphic screen. There is no local temperature indication for CC HX Outlet temperature.

D - Plausible: There are evolutions where valves are throttled locally while local observation of flow and/or temperatures is required.

Test ID: 347808 09/15/2021 38 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q14 User ID RE10056-N05 System ID 2169368 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # Electrical Schematic 6E-1-4030SX27, Rev. L, C&ID M-2066 Sht 3 Detail A, Rev. P Training Objective T.OA18-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification The question meets the K/A, requires examinee ability to operate and monitor SX to CC HX outlet valve and parameters by knowing where they are located.

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam.

The question meets Tier 1 criteria because it requires ability to perform procedure steps that control plant equipment to mitigate an abnormal situation.

K/A Reference(s)

APE.062.AA1.06 Safety Function 4 Tier 1 Group 1 RO Imp: 2.9 SRO Imp: 2.9 Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): (CFR 41.7 / 45.5 / 45.6)

Control of flow rates to components cooled by the SWS Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Test ID: 347808 09/15/2021 39 of 229

2021 RO/SRO NRC Exam Test Key Cross Reference Links None Test ID: 347808 09/15/2021 40 of 229

2021 RO/SRO NRC Exam Test Key Question 15 ID: 2169369 Points: 1.00

Unit 1 is at 100% power.

Normal charging is aligned to the 1B RC loop.

1A Regenerative HX is in service.

A malfunction results in isolation of Instrument Air (IA) to Unit 1 Containment.

Annunciator 1-7-A2, RCP SEAL WTR INJ FLTR P HIGH, is in alarm.

Which one of the following valve's response to the loss of IA to containment, caused the alarm?

A. 1CV8142, NO.1 SEAL BYP ISOL VLV B. 1CV8146, CHG TO RC LOOP 1B ISOL VLV C. 1CV8324A, CHG TO REGEN HX ISOL VLV D. 1CV182, CHG HDR BACK PRESS CONT VLV Answer C Answer Explanation A - Plausible: 1CV8142, NO.1 SEAL BYP ISOL VLV, is incorrect. 1CV8142 is normally closed and fails closed on loss of air. Therefore, would not affect RCP seal injection during a loss of instrument air. This would be correct if the 1CV8142 failed open.

B - Plausible: 1CV8146, CHG TO RC LOOP 1B ISOL VLV is incorrect. 1CV8146 is normally open in the given plant alignment and fails open on a loss of air. This would be correct if the 1CV8146 failed closed.

C - Correct: 1CV8324A, CHG TO REGEN HX ISOL VLV is correct. 1CV8324A fails closed on loss of instrument air to containment. Consequently, all charging flow is directed through the seal injection flow path causing Annunciator 1-7-A2 to alarm.

D - Plausible: 1CV182, CHG HDR BACK PRESS CONT VLV is incorrect. 1CV182 is outside Containment so it would not lose air. A failure of 1CV182 will affect seal injection parameters. The examinee may plausibly conclude that if 1CV182 failed it would cause the given annunciator.

Test ID: 347808 09/15/2021 41 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q15 User ID RE10065-AA2.08-15 System ID 2169369 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 6E-1-4030CV24, Rev. K, BAR 1-7-A2, Rev. 4 Training Objective S.CV1-16-E Byron Previous 2 NRC Exam Use None References Provided None K/A Justification This question meets the K/A because the examinee must determine the failure mode of associated valves and if that failure mode would result in the subject annunciator.

SRO-Only Justification Not applicable Additional Information Bwd 2019 NRC exam The question meets Tier 1 criteria because it requires assessment of the integrated plant response to emergency or abnormal situations crossing several plant systems and/or safety functions. This question tests applicants' knowledge of the response of the Instrument Air, CVCS and annunciator systems during an abnormal situation.

K/A Reference(s)

APE.065.AA2.08 Safety Function 8 Tier 1 Group 1 RO Imp: 2.9* SRO Imp: 3.3 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: (CFR: 43.5 / 45.13)

Failure modes of air-operated equipment Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Test ID: 347808 09/15/2021 42 of 229

2021 RO/SRO NRC Exam Test Key Cross Reference Links None Test ID: 347808 09/15/2021 43 of 229

2021 RO/SRO NRC Exam Test Key Question 16 ID: 2169564 Points: 1.00

Byron Station has been notified that the State Estimator alarm predicts a potential degraded grid condition in the event of a Byron unit trip.

The crew is performing 0BOA ELEC-1, DEGRADED SWITCHYARD VOLTAGE, Step 4, CHECK 4KV NON-ESF BUS LOADING (SAT).

Which of the following parameters are MULTIPLIED TOGETHER to calculate NON-ESF BUS LOADING on the SATs?

A. Bus volts and SAT feed amps B. UAT watts and bus volts C. SAT feed amps and generator VARS D. Generator VARS and UAT watts Answer A Answer Explanation A is correct, 0BOA ELEC-1 calculates bus loading using bus volts and SAT feed amps. These meters are read from 1PM01J. The distractors (gen VARS and UAT watts) are also on 1PM01J meters but are not used in the calculation. While it would not be expected that the examinee know which meters are used in the procedure from memory, he/she should be able to deduce the correct answer given their previous knowledge of electrical theory and term definitions.

B is incorrect, Plausible because the distractors (gen VARS and UAT watts) are also on 1PM01J meters but are not used in the calculation.

C is incorrect, Plausible because the distractors (gen VARS and UAT watts) are also on 1PM01J meters but are not used in the calculation.

D is incorrect, Plausible because the distractors (gen VARS and UAT watts) are also on 1PM01J meters but are not used in the calculation.

Test ID: 347808 09/15/2021 44 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q16 User ID RE10077-N01 System ID 2169564 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 0BOA ELEC-1, Rev.17 Training Objective T.OA01A-04 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of interrelations between grid disturbances and indicators.

SRO-Only Justification N/A Additional Information From Bwd 2009 NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

APE.077.AK2.03 Safety Function 6 Tier 1 Group 1 RO Imp: 3.0 SRO Imp: 3.1 Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following:

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

Sensors, detectors, indicators Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 45 of 229

2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 46 of 229

2021 RO/SRO NRC Exam Test Key Question 17 ID: 2169371 Points: 1.00

An RCS LOCA occurred on Unit 1.

1SI8811A and B, CNMT SUMP ISOL VLVs, are STUCK CLOSED.

1BCA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, was entered.

Minimum ECCS flow to remove decay heat has been established per 1BCA-1.1.

In accordance with 1BCA-1.1, what plant parameter will require the NSO to raise RCS make-up flow?

A. Pressurizer level drops to 0%.

B. RCS subcooling drops to +40°F.

C. Hot leg wide range temperatures rise.

D. Core exit thermocouples rise.

Answer D Answer Explanation A is incorrect: This is a plausible distractor because Pressurizer level is used in determining SI re-initiation criteria in other emergency procedures (1BEP-3), but not in 1BCA-1.1 B is incorrect: This is a plausible distractor because +50°F subcooling is the criteria on the 1BCA-1.1 CAS for determining whether to completely terminate ECCS flow or to establish minimum ECCS flow.

C is incorrect: This is a plausible distractor because Hot Leg temperatures may rise with the given conditions however, Hot leg wide range temperatures are not used because they can be an unreliable indicator of core conditions during a LOCA due to specific RCS flow conditions.

D - Correct: 1BCA-1.1 Continuous Action Summary requires the operator to raise RCS make-up flow if either the CETCs rise or if the RVLIS plenum region drops below 15%. This is less restrictive than criteria used in other emergency procedures to raise ECCS flow because of the objective to conserve RWST water.

Test ID: 347808 09/15/2021 47 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q17 User ID RE1WE11-N01 System ID 2169371 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1BCA-1.1, Rev. 302 Training Objective T.CA2-05 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification The question meets the K/A, requires examinee knowledge of indications and the response procedure during a loss of emergency coolant recirc event.

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

P2.4.31 Safety Function 6 Tier 3 Group RO Imp: 4.2 SRO Imp: 4.1 Knowledge of annunciator alarms, indications, or response procedures.

(CFR: 41.10 / 45.3)

GE.4.5.E11 Safety Function 4 Tier 1 Group 1 RO Imp: SRO Imp:

Loss of Emergency Coolant Recirculation Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 48 of 229

2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 49 of 229

2021 RO/SRO NRC Exam Test Key Question 18 ID: 2169372 Points: 1.00

A Unit 1 loss of heat sink has occurred.

The crew is establishing RCS Bleed and Feed in accordance with 1BFR-H.1, LOSS OF SECONDARY HEAT SINK, steps 15 through 18.

BOTH PZR PORVs were manually OPENED.

Why are PZR PORVs manually opened (instead of being allowed to automatically cycle) during performance of Bleed and Feed in 1BFR-H.1?

A. Ensure adequate ECCS flow to maintain core cooling.

B. Prevent lifting PZR safety valves.

C. Enhance mixing of ECCS flow in the reactor core to minimize possibility of PTS.

D. Minimize cycling of PZR PORVs.

Answer A Answer Explanation A is correct: Per WOG background document, ECCS capability of Westinghouse PWRs at the PORV open setpoint pressure is not sufficient to ensure core cooling using feed and bleed. Therefore, the PORV is manually opened prior to reaching the auto open setpoint to ensure a success path to core cooling.

B is incorrect: Plausible because it is a correct reason for opening PORV during other plant conditions.

C is incorrect: Plausible because it is a concern during SI for localized excessive cooldown.

D is incorrect: Plausible because it is a concern for minimizing risk of equipment damage.

Question Information Topic 2021 NRC Q18 User ID RE1WE05-002 System ID 2169372 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

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2021 RO/SRO NRC Exam Test Key Question Type Bank Difficulty Technical Reference and Revision # FR-H.1 WOG BD, Rev 301 Training Objective T.FR03-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to know operational implications for remedial actions during loss of heat sink event.

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s) 4.5.E05.EK1.3 Safety Function 4 Tier 1 Group 1 RO Imp: 3.9 SRO Imp: 4.1 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Secondary Heat Sink) (CFR: 41.8 / 41.10, 45.3)

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink).

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 19 ID: 2169567 Points: 1.00 At 1000:

A power descension was in progress.

Control rods began inserting in Auto as expected.

Rod H-8 in group 2 of CBD did NOT move with the rest of the bank.

The Rod Bank Select Switch was placed in Manual, and the power descension halted.

The crew entered 2BOA ROD-3, DROPPED OR MISALIGNED ROD.

Rod H-8 is determined to be 8 steps above the rest of the bank.

At 1200:

Unit 2 is at 80% power.

Repairs have been made to the rod control system and power level is acceptable for rod recovery.

Per 2BOA ROD-3, which of the following is/are necessary to recover Rod H-8?

The crew will place the Rod Bank Select Switch in A. CBD, AND disconnect the lift coils for ALL rods in group 1 of CBD ONLY.

B. CBD, AND disconnect the lift coils for ALL rods in CBD EXCEPT H-8.

C. Manual, AND disconnect the lift coil for rod H-8 ONLY.

D. CBD ONLY.

Answer B Answer Explanation A - Plausible, because the stuck rod is in group 2 (vs. group 1), however this would still move the unaffected rods in the affected group.

B - Correct: 2BOA ROD-3 directs realigning rod to bank by disconnecting lift coils for all other rods in affected bank and placing rod bank select switch to affected bank. This accounts for all of the switches that have to be operated in the MCR before recovering the rod. This allows for only the dropped rod to be withdrawn, and the unaffected rods will not be withdrawn with the lift coils disconnected.

C - Plausible: This configuration would realign the affected bank to the stuck rod, however 2BOA ROD-3 directs rod to bank realignment. Re-aligning bank to rod would have an undesirable larger reactivity change.

D - Plausible, because the stuck rod is in CBD, however this alignment would not realign the affected rod to its bank. Instead it would cause all the CBD rods to move simultaneously with the affected rod still misaligned.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q19 User ID RE2005-N14-58 System ID 2169567 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 2BOA ROD-3, Rev. 113 Training Objective T.OA34-03 Previous 2 Byron Exam Use None References Provided None K/A Justification The question meets the K/A because examinee must have the ability to operate the CRDS during a stuck control rod event. This is RO level because the RO should be able to apply rod control system knowledge during the performance of an AOP.

SRO-Only Justification Not Applicable Additional Information From Bwd 2019 NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

APE.005.AA1.01 Safety Function 1 Tier 1 Group 2 RO Imp: 3.6 SRO Imp: 3.4 Ability to operate and / or monitor the following as they apply to the Inoperable / Stuck Control Rod: (CFR 41.7 /

45.5 / 45.6)

CRDS Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 54 of 229

2021 RO/SRO NRC Exam Test Key Question 20 ID: 2169568 Points: 1.00

Unit 1 is in MODE 2, reactor start up in progress.

All U-1 systems are normally aligned for this mode.

Unit 2 is at 100% power.

The following sequence of events occurs:

Unit 1 offsite power is LOST.

All equipment operates as designed.

The crew is performing 1BEP ES-0.1, REACTOR TRIP RESPONSE, after determining SI was NOT required.

At step 1.b, CHECK RCS TEMPERATURE RESPONSE NORMAL, it is determined that emergency boration is required per 1BOA PRI-2, EMERGENCY BORATION.

Non-ESF buses are still DE-ENERGIZED.

With the above conditions, how will the NSO Borate the RCS?

A. BAST via 1CV8104, EMER BORATION VALVE, and normal charging header.

B. BAST via 1CV110A, BORIC ACID TO BLNDR VLV and 1CV110B, BORIC ACID BLNDR TO CHG PMPS VLV and normal charging header.

C. RWST via 1CV112D and/or 1CV112E, RWST TO CHG PUMP SUCT VLVS and normal charging header.

D. RWST via 1CV112D and/or 1CV112E, RWST TO CHG PUMP SUCT VLVS and high head injection header.

Answer C Answer Explanation A is incorrect, no power is available to boric acid pump. Plausible because it is one of the normal boration flow paths in 1BOA PRI-2.

B is incorrect, no power is available to boric acid pump. Plausible because it is one of the normal boration flow paths in 1BOA PRI-2.

C is correct, BA pump is powered from a non-ESF bus, so it is not available for flow through the normal boration flow path or through 1CV8104. Non-ESF buses lost power when the LOOP occurred in mode 2.

Non-ESF power does not get restored until later in 1BEP ES-0.1. Boration flow through 1CV112D & E (ESF powered) from the RWST is the only option. Normal charging header is available because all equipment operates as designed and 1BOA PRI-2 directs boration via the normal charging header prior to attempting boration through the high head injection header.

D is incorrect, plausible because this alignment is an attachment in 1BOA PRI-2 if the normal charging header is not available.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q20 User ID RS20004-N01 System ID 2169568 Status Active Point Value 1.00 Time (min) 1 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1BOA PRI-2, Rev. 108 Training Objective T.OA13-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to determine if boron flow is available from the boric acid transfer pump.

SRO-Only Justification N/A Additional Information From Bwd 2009 NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

APE.024.AA2.01 Safety Function 1 Tier 1 Group 2 RO Imp: 3.8* SRO Imp: 4.1 Ability to determine and interpret the following as they apply to the Emergency Boration: (CFR: 43.5 / 45.13)

Whether boron flow and/or MOVs are malfunctioning, from plant conditions Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 57 of 229

2021 RO/SRO NRC Exam Test Key Question 21 ID: 2169375 Points: 1.00

Unit 1 is in Mode 2, with a reactor startup in progress.

Reactor power is approx. 500 CPS in the source range.

Then:

Source Range channel N32 fails to zero.

Annunciator 1-10-B1, SR NON-OPERATE, alarms.

What, if any, of the following technical specification entries is/are required?

LCO 3.3.1, Reactor Trip System Instrumentation LCO 3.3.2, Engineered Safety Feature Actuation System Instrumentation A. Neither B. LCO 3.3.1 ONLY C. LCO 3.3.2 ONLY D. LCOs 3.3.1 AND 3.3.2 Answer B Answer Explanation A - Incorrect: This would be correct if reactor power was above the P-6 setpoint. However, 500 CPS is approximately one decade below P-6.

B - Correct: TS 3.3.1 is applicable in Mode 2 below P-6.

C - Incorrect: Plausible because source range NIs are interlocked with permissive P-6. Several other permissives interlocks (P-4, P-11, P-12) are applicable to TS 3.3.2. Additionally, TS 3.3.1 and 3.3.2 are commonly confused by novice applicants. TS 3.3.1 and 3.3.2 both are instrumentation tech specs. The instrumentation signals are for both functions are similiarly processed through SSPS input bays and logic cabinets.

D - Incorrect: Plausible because this answer is a combination of the correct answer and a plausible distractor.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q21 User ID RE20032-N04 System ID 2169375 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # TS 3.3.1, Amendment 212 Training Objective S.NI1-14 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to recognize system parameters that are entry level conditions for Tech Specs.

SRO-Only Justification N/A Additional Information The question meets Tier 1 criteria because it requires diagnosis that leads to selection of the procedures that should be used to respond to the evolution. This question requires a tech spec entry assessment to an abnormal condition which is an administrative mitigation action.

K/A Reference(s)

P2.2.42 Safety Function 1 Tier 3 Group RO Imp: 3.9 SRO Imp: 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)

GE.4.0.APE.032 Safety Function 7 Tier 1 Group 2 RO Imp: SRO Imp:

Loss of Source Range Nuclear Instrumentation Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 60 of 229

2021 RO/SRO NRC Exam Test Key Question 22 ID: 2169376 Points: 1.00

Unit 2 was at 100% power.

SG pressures were 885 psig.

Subsequently, a 20 gpm SG tube leak (cracked tube) was identified with stable normal Unit 100%

power parameters.

The crew entered 2BOA SEC-8, SG TUBE LEAK, and performed a controlled Unit shut down.

Currently, Unit 2 is in Mode 3 at 0% power.

SG pressures are 1092 psig.

RCS pressure is 2235 psig Assume the tube crack physical size has NOT changed.

What is the approximate current leak rate at 0% power?

A. 16 gpm B. 18 gpm C. 22 gpm D. 24 gpm Answer B Answer Explanation A - Incorrect: See answer explanation below. Plausible because if calculation is made using the quotient of the DPs (vs. quotient of the DPs sq. roots), the calculation will equal 16.9 gpm.

B - Correct: Leak flow will drop to 18.4 gpm.

Theory, flow is proportional to the square root of the delta pressure.

- RCS pressure remains constant at 2235 psig.

- U-2 SG pressure at 100% power is approx. 885 psig.

- U-2 SG pressure at 0% power is approx. 1092 Leak flow @ 100% / Leak flow @ 0% = Sq. root of 100% DP / Sq. root of 0% DP.

Therefore, Leak flow @ 0% = Leak flow @ 100% x (Sq. root of 0% DP / Sq. root of 100% DP) =

20 gpm x (Sq. root of 1143 / Sq. root of 1350) = 20 gpm x.92 = 18.4 gpm.

C - Incorrect: This flow range is change in opposite direction of correct answer. Common misconception of SG pressures dropping as unit power drops. This error will equal 21.7 gpm.

D - Incorrect: This flow range is change in opposite direction of correct answer. Common misconception of SG pressures dropping as unit power drops. Additionally, this flow range calculation uses the same Test ID: 347808 09/15/2021 61 of 229

2021 RO/SRO NRC Exam Test Key calculation error as distractor A. The errors combined will equal 23.6 gpm.

Question Information Topic 2021 NRC Q22 User ID RE20037-N01 System ID 2169376 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.14 Principles of heat transfer thermodynamics and fluid 10CFR55 Content mechanics.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # National Academy For Nuclear Training LP, Fluid Statics and Dynamics, Rev.3.2 Training Objective TLO 1, Explain the fundamental properties of fluids and closed fluid systems Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to have knowledge of operational implication of leak rate vs. pressure during SGTL.

SRO-Only Justification N/A Additional Information The question meets Tier 1 criteria because it requires assessment of the progression of an abnormal event.

K/A Reference(s)

APE.037.AK1.02 Safety Function 3 Tier 1 Group 2 RO Imp: 3.5 SRO Imp: 3.9 Knowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak:

CFR 41.8 / 41.10 / 45.3)

Leak rate vs. pressure drop Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 23 ID: 2169377 Points: 1.00 An audible alarm on the RMS is received as indicated below.

(Analyze each evolution separately and assume each evolution causes local radiation levels to rise above the alert setpoint on the nearest area detector on the same elevation)

Which of the following plant evolutions (based on plant location), would be most likely to cause the alarm?

A. A reactor coolant filter is being removed from its filter vault.

B. A Spent Fuel Pit Pump is leaking at the discharge check valve.

C. A radwaste vendor demineralizer resin bed is being transferred to a bulk radwaste liner.

D. Radiography of the U-1 CC surge tank vent valve line.

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2021 RO/SRO NRC Exam Test Key Answer A Answer Explanation A is correct, The area rad monitor channel 3AS110 in alert status is located in the aux bldg, 401' elevation on the Unit 1 side. This is the general area where RC filter vaults are opened and the filters removed for changing. The distractors would alarm different detector channels on the same RMS Grid 4 screen. BAR RMS-4-0AR60J lists radwaste filter pulls as the probable cause for this alarm.

B is incorrect, Plausible because the Spent Fuel Pit Pump is located on the 401' elevation in the Fuel Handling Building. This is the same elevation however, the radwaste building detector icons are grouped in a separate section on Grid 4 of the RMS.

C is incorrect, Plausible because the radwaste vendor demin and bulk resin liner loading area is on 401' elevation in the Solid Radwaste Bldg. This is the same elevation however, the Fuel Handling Building detector icons are grouped in a separate section on Grid 4 of the RMS.

D is incorrect, the CC surge tank vent line is on the 426' elevation (above the filter changing area). This can easily be confused with the alarming detector if the candidate associates the RMS icons with the elevation labeling above the icon (vs. the elevation labeling below the icon).

Question Information Topic 2021 NRC Q23 User ID RG30014-N01 System ID 2169377 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.11 Purpose and operation of radiation monitoring systems, 10CFR55 Content including alarms and survey equipment.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BAR RMS-4-0AR60J, Rev. 0 Training Objective S.AR1-09 Previous 2 Byron NRC Exams Use None References Provided RMS Grid 4 screen shot in question stem K/A Justification Question meets the K/A, requires examinee knowledge of interrelations between ARM alarm and detector location.

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2021 RO/SRO NRC Exam Test Key Additional Information From Bwd 2016 NRC exam.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

APE.061.AK2.01 Safety Function 7 Tier 1 Group 2 RO Imp: 2.5* SRO Imp: 2.6*

Knowledge of the interrelations between the Area Radiation Monitoring (ARM) System Alarms and the following:

(CFR 41.7 / 45.7)

Detectors at each ARM system location Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 24 ID: 2169378 Points: 1.00

Unit 1 reactor was at 100% power.

A reactor trip and SI then occurred.

The BOP operator is currently performing 1BEP-0, REACTOR TRIP OR SI, Attachment B, step 5, VERIFY CNMT ISOLATION PHASE A.

Group 3 CNMT Isol monitor lights are lit EXCEPT the following 2 lights are DARK:

- WO056B (1B + 1D CHILL WTR OUTLET CNMT ISOL VLV)

- CV8100 (SEAL WTR RTN CNMT ISOL VLV)

Per 1BEP-0, the RO then dispatches an EO to locally close ONLY 1CV8100.

Why is 1WO056B NOT required to be locally closed also per 1BEP-0?

A. The EO would be required to make a containment entry.

B. The WO system is not a potentially contaminated system.

C. The WO system pumps are already tripped.

D. The WO penetration has an inside containment check valve, so the penetration is isolated.

Answer A Answer Explanation A - Correct: The step 5 RNO actions for Phase A Isol valves not closed is: 1) Manually actuate Phase A (no effect without power) 2) Manually close valves (from MCR) (no effect without power) 3) Locally close the valves located outside containment. An EO would not be dispatched to 1WO056B because it is inside containment and a containment entry would not be desirable under emergency conditions.

B - Plausible: Although the WO system is not normally contaminated (while CV system is), 1BEP-0 does not differentiate between normally contaminated and uncontaminated systems because 1BEP-0, attachment B, step 5 is a verification step rather than an analysis step. To justify the plausibility of this distractor, PWROG-14043-NP the PWR WOG Emergency Response Guideline Based Critical Tasks, lists CT-11, closing some containment isolation Phase A valves as a critical task. Two of the plant conditions referenced in the bases are:

"Fluid is flowing into the auxiliary building through at least one of the following pathways:

- At least one unisolated Phase A penetration that is in direct communication with the RCS.

- At least one unisolated Phase A penetration that is in direct communication with the containment atmosphere.

Therefore, while 1BEP-0 does not determine the need for containment isolation based upon the potential contamination in the system, the bases for considering the manual isolation of each system as a "critical task" does account for the potential of the system being contaminated.

C - Plausible: Although the WO system pumps have tripped due to at least one containment isolation valve closed in both train A and B flow paths, that is not criteria for whether or not containment isolation is Test ID: 347808 09/15/2021 66 of 229

2021 RO/SRO NRC Exam Test Key required.

D - Plausible: The WO inlet penetrations are isolated by an inside containment check valve combined with an outside containment isolation valve. However, the 1WO056B is on the WO outlet penetration, and 1BEP-0 does not differentiate between double MOVs or single MOV isolated (with a check valve) penetrations.

Question Information Topic 2021 NRC Q24 User ID RE20069-N03 System ID 2169378 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BEP-0, Rev. 304 Training Objective 3D.EP-01-D Previous Exam Use None References Provided None K/A Justification Meets the KA by requiring candidate knowledge of reason for EOP guidance on a failure of containment integrity valves to close.

SRO-Only Justification N/A Additional Information The question meets Tier 1 criteria because it requires assessment of the integrated plant response to emergency or abnormal situations crossing several plant systems and/or safety functions. This question tests an applicants knowledge of the response of the WO and ESF systems during an emergency situation.

K/A Reference(s)

APE.069.AK3.01 Safety Function 5 Tier 1 Group 2 RO Imp: 3.8* SRO Imp: 4.2 Knowledge of the reasons for the following responses as they apply to the Loss of Containment Integrity: (CFR 41.5,41.10 / 45.6 / 45.13)

Guidance contained in EOP for loss of containment integrity Test ID: 347808 09/15/2021 67 of 229

2021 RO/SRO NRC Exam Test Key Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 25 ID: 2169636 Points: 1.00

Unit 1 tripped from 100% power.

The transient caused SG pressures to RISE.

Later in the transient, the STA reports status tree YELLOW flow path on HEAT SINK.

The crew enters the associated procedure, 1BFR-H.2 RESPONSE TO SG OVERPRESSURIZATION.

A note in 1BFR-H.2 reads, "Throughout this procedure, "AFFECTED" refers to any SG in which pressure is greater than ____ PSIG."

A. 1005 B. 1092 C. 1115 D. 1235 Answer D Answer Explanation A is incorrect. Plausible because 1005 psig is the 100% power nominal design pressure for Unit 1 SGs.

B is incorrect. Plausible because 1092 psig is the 0% power nominal design pressure for Unit 1 SGs and the controlling setpoint for steam dumps to control post trip SG pressure.

C is incorrect. Plausible because 1115 psig is the opening setpoint of the SG PORVs.

D is correct. The second note in 1BFH-H.2 reads "Throughout this procedure, "AFFECTED" refers to any SG in which pressure is greater than 1235 PSIG."

Question Information Topic 2021 NRC Q25 User ID RS20035-N05 System ID 2169636 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BFR-H.2, Rev. 300 Training Objective T.FR03-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor instrumentation during a SG over pressure event.

SRO-Only Justification N/A Additional Information The question is RO level because RO applicants are responsible for information in notes and cautions within AOPs and EOPs.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s) 4.5.E13.EA1.1 Safety Function 4 Tier 1 Group 2 RO Imp: 3.1 SRO Imp: 3.3 Ability to operate and / or monitor the following as they apply to the (Steam Generator Overpressure) (CFR: 41.7 /

45.5 / 45.6)

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 26 ID: 2169380 Points: 1.00

Unit 1 is in MODE 4.

RCS Pressure is 350 psig.

SI Accumulators are ISOLATED.

A Containment Area Rad monitor alarmed and the crew noted the following:

PZR Level is DROPPING.

Letdown is ISOLATED.

Charging flow is 200 gpm.

Because it contains the specific actions to mitigate these conditions, what procedure will the crew enter?

A. 1BOA S/D-2, SHUTDOWN LOCA B. 1BOA PRI-1, EXCESSIVE PRIMARY PLANT LEAKAGE C. 1BOA PRI-4, HIGH REACTOR COOLANT ACTIVITY D. 1BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT Answer A Answer Explanation A is correct, 1BOA S/D-2 is written for modes 3 and 4 after SI accumulators are isolated. Mitigation steps of S/D-2 will be to manually restore and align ECCS, then cool down the plant and depressurize.

B is incorrect, Plausible because 1BOA PRI-1 is written for RCS leaks. However, 1BOA PRI-1 is written for RCS leaks in Mode 1-4 that are within the capability of the CV system to maintain pressurizer level, with SI accumulators not isolated. If the crew chose to enter 1BOA PRI-1, then at step 4 RNO transition would be made to 1BOA S/D-2 because plant was not in the condition of applicability listed in 1BOA PRI-

1. Therefore, 1BOA PRI-1 is incorrect because the mitigation steps for this situation are not contained in it.

Choice C is incorrect, Plausible because a containment rad monitor is in alarm. However, 1BOA PRI-4 is applicable for the gross failed fuel monitor alarm, not a containment area monitor.

Choice D is incorrect, Plausible because 1BEP-1 is written for RCS leaks. However, 1BEP-1 is not a direct entry procedure and is only used after a reactor trip and SI.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q26 User ID RE2WE16-N04 System ID 2169380 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 1BOA S/D-2, Rev. 111 Training Objective T.OA35-02 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to select appropriate procedure during abnormal event initiated by high containment radiation.

SRO-Only Justification N/A Additional Information From 2009 Bwd NRC exam.

The question meets Tier 1 criteria because it requires diagnosis that leads to selection of the procedures that should be used to respond to the evolution.

K/A Reference(s) 4.5.E16.EA2.1 Safety Function 9 Tier 1 Group 2 RO Imp: 2.9 SRO Imp: 3.3 Ability to determine and interpret the following as they apply to the (High Containment Radiation) (CFR: 43.5 /

45.13)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 73 of 229

2021 RO/SRO NRC Exam Test Key Question 27 ID: 2169381 Points: 1.00

A manual reactor trip and SI were initiated from 100% power due to a faulted SG on Unit 1.

1BFR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION, has been implemented.

The following plant conditions exist 25 minutes after the SI.

RCS cold leg temperatures are 235°F and stable.

RCS pressure is 2000 psig and stable.

Containment pressure is 5.5 psig.

CETC indication is 350°F.

ECCS flow has been terminated.

The operators are preparing to depressurize the RCS per 1BFR P.1 step 16c.

With these conditions, the RCS depressurization should be stopped at which of the following pressures?

[REFERENCE PROVIDED]

A. 225 psig B. 250 psig C. 275 psig D. 300 psig Answer B Answer Explanation A is incorrect: This would be correct if 1BFR P.1-5 normal containment curves are used.

B is Correct: Answer is based on Figure 1BFR P.1-6 between the curves for adverse containment.

Distractors are based on using wrong curve or using curves incorrectly.

C is incorrect: This would be correct if normal containment curve is used and the lowest pressure is selected that is to the left of the +10°F curve. Plausible because most subcooling charts have an "Acceptable" region that is to the left of the curves and an "Unacceptable" region to the right of the curves. However, Figure 1BFR P.1-5 and P.1-6 are designed such that the target pressure is between the curves. Using 1BFR P.1-5 in the same manner as a normal subcooling curve is used will lead to this incorrect answer.

D is incorrect: This would be correct if adverse containment curve is used and the lowest pressure is selected that is to the left of the +10°F curve. Plausible because most subcooling charts have an "Acceptable" region that is to the left of the curves and an "Unacceptable" region to the right of the curves. However, Figure 1BFR P.1-5 and P.1-6 are designed such that the target pressure is between the curves. Using 1BFR P.1-6 in the same manner as a normal subcooling curve is used will lead to this Test ID: 347808 09/15/2021 74 of 229

2021 RO/SRO NRC Exam Test Key incorrect answer.

Question Information Topic 2021 NRC Q27 User ID BYLC3DFR05B005 System ID 2169381 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number OPEN Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1BFR-P.1, Rev. 301 Training Objective T.FR04-04-A Previous 2 Byron NRC Exams Use None References Provided 1BFR-P.1, Page 14 (step 16 c.)

FIGURE 1BFR P.1-5 FIGURE 1BFR P.1-6 K/A Justification Question meets the K/A, requires examinee ability to interpret graph during PTS event.

SRO-Only Justification N/A Additional Information From Byron LOR bank.

The question meets Tier 1 criteria because it requires information contained in the sites procedures, including ARPs, AOPs, EOPs, and their associated bases documents.

K/A Reference(s)

P2.1.25 Safety Function 9 Tier 3 Group RO Imp: 3.9 SRO Imp: 4.2 Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10 / 43.5 / 45.12)

GE.4.5.E08 Safety Function 4 Tier 1 Group 2 RO Imp: SRO Imp:

Pressurized Thermal Shock Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Test ID: 347808 09/15/2021 75 of 229

2021 RO/SRO NRC Exam Test Key Cross Reference Links None Test ID: 347808 09/15/2021 76 of 229

2021 RO/SRO NRC Exam Test Key Question 28 ID: 2169382 Points: 1.00

Unit 1 is at 28% reactor power.

Rod bank select switch is in manual.

The 1B RCP trips due to an overcurrent condition.

With NO operator action, an automatic reactor trip will __ 1 __ and T will __ 2 __ in the 1A, 1C, and 1D loops.

A. 1. NOT occur

2. rise B. 1. NOT occur

2. lower C. 1. occur

2. rise D. 1. occur

2. lower Answer A Answer Explanation A is correct. A reactor trip will not occur with reactor power less than 30%. Without rod motion or operator action, T for the unaffected loops will rise because only 3 SGs will be supplying the steam that 4 SGs were. The reactor coolant coming into the core from the SGs will be colder because the unaffected SGs will be taking more steam out to meet the steam demand.

B is incorrect. Plausible because it is the opposite T response.

C is incorrect. Plausible because a reactor trip would occur above 30% power. A reactor trip will not occur below 30% power.

D is incorrect. Plausible because a reactor trip would occur above 30% power. A reactor trip will not occur below 30% power and because it is the opposite T response.

Red text was added during exam administration in response to an applicants question.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q28 User ID RS2002-N14-01 System ID 2169382 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BAR 1-13-B3, Rev. 4, BAR 1-14-A4, Rev.53 Training Objective S.RC1-06 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the effect of an RCP malfunction on RCS T.

SRO-Only Justification N/A Additional Information From 2014 Bwd NRC exam K/A Reference(s)

SF4.003.K3.01 Safety Function 4 Tier 2 Group 1 RO Imp: 3.7 SRO Imp: 4.0 Knowledge of the effect that a loss or malfunction of the RCPS will have on the following: (CFR: 41.7 / 45.6)

RCS Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 78 of 229

2021 RO/SRO NRC Exam Test Key Question 29 ID: 2169383 Points: 1.00

Unit 1 is at 100% power.

A plant transient has caused Unit 1 VCT level to rise to >95%.

1CV112A, LTDWN TO VCT OR HUT DIVERT VLV, is FULL DIVERT to HUT, in AUTO.

The transient has been mitigated and VCT level begins to slowly lower.

What is the HIGHEST VCT level that 1CV112A will FULLY realign to the VCT?

A. 94%

B. 72%

C. 54%

D. 36%

Answer B Answer Explanation A - Incorrect: 1LT-185 will override the modulation signal from 1LT-112 and maintain 1CV12A full open until VCT level is <73%. Plausible because 95% is the full open setpoint.

B - Correct: 1CV112A is controlled by 2 independent level transmitters, 1LT-112 and 1LT-185.

1LT-112 will modulate 1CV112A between 73% and 95%.

1LT185 will fully open 1CV112A at 95% and (once actuated on high level) will maintain 1CV112A full open until VCT level is <73% (reset setpoint). Therefore, 1LT-185 will override the modulation signal from 1LT-112 and maintain 1CV12A full open until VCT level is <73%.

C - Incorrect: Plausible because 1LT-112 will modulate 1CV112A between 73% and 95% however, 55%

is the VCT auto make up "off" setpoint.

D - Incorrect: Plausible because 37% is the VCT auto make up "on" setpoint.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q29 User ID RS10004-N06 System ID 2169383 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # BAR 1-9-A2, Rev. 11 Training Objective S.CV1-11 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the interlocks for the letdown divert valve.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF1.004.K4.14 Safety Function 1 Tier 2 Group 1 RO Imp: 2.8* SRO Imp: 3.2 Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

Control interlocks on letdown system (letdown tank bypass valve)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 80 of 229

2021 RO/SRO NRC Exam Test Key Question 30 ID: 2169384 Points: 1.00

Unit 1 is at 100% power.

The 1A Letdown Heat Exchanger is online.

1CC130A, LTDOWN HX TEMP CONTROL VLV, failed full CLOSED due to a controller failure.

Annunciator 1-9-E2, LTDWN TEMP HIGH, has just alarmed.

What will be the INITIAL mitigating action to protect the letdown demineralizers for this event?

A. NO automatic actions will occur. Manual actions per a BAR procedure are required.

B. Automatic letdown isolation by the letdown orifice isolation valves.

C. Letdown flow to the VCT automatically bypasses the demineralizers.

D. Letdown flow automatically bypasses the demineralizers and is directed to the HUT.

Answer C Answer Explanation A - Plausible: Misconception of automatic system operation. Some valve failures require manual mitigation actions per the appropriate BAR. BAR 1-9-E2, LTDWN TEMP HIGH, subsequent actions is to manually isolate letdown if the automatic actions do not occur.

B - Plausible: Misconception of automatic system operation. Other system failures will cause auto letdown isolation. Examples are phase A isolation or low pressurizer level.

C - Correct: 1CV129 will auto divert letdown flow around the letdown demins at letdown heat exchanger outlet temperature of 133°F.

D - Plausible: Misconception of automatic system operation. VCT high level will cause letdown flow to be diverted to HUTs.

Question Information Topic 2021 NRC Q30 User ID RS10004-N05 System ID 2169384 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BAR 1-9-E2, Rev. 2 Training Objective S.CV1-16-D Previous Exam Use None References Provided None K/A Justification The question meets the K/A, requires examinee knowledge of effect of a malfunction which causes letdown to exceed demineralizer temperature limits. .

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam K/A Reference(s)

SF1.004.K6.20 Safety Function 1 Tier 2 Group 1 RO Imp: 2.5 SRO Imp: 3.1 Knowledge of the effect of a loss or malfunction on the following CVCS components: (CFR: 41.7 / 45.7)

Function of demineralizer, including boron loading and temperature limits Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 82 of 229

2021 RO/SRO NRC Exam Test Key Question 31 ID: 2169385 Points: 1.00

Unit 1 is in Mode 4.

RCS cold leg temperatures are 340°F.

RCS boron concentration is 1590 ppm.

RCS pressure is 345 psig.

1A RH train boron concentration is 1250 ppm.

1B RH train is aligned for injection.

What would result from placing the 1A RH train in SHUTDOWN COOLING with the current boron concentration?

A. A reduction in shutdown margin.

B. An inadvertent entry into mode 3.

C. Boron plateout on the 1A RH HX.

D. An increase in shutdown margin.

Answer A Answer Explanation A is correct: 1A RH train boron concentration is 1250 ppm, placing it online would reduce the RCS boron concentration, and therefore lower SDM.

B is incorrect: Plausible because online at power diluting the RCS this much would cause a large temperature rise. However, placing an RH train online would reduce RCS temperature, not raise it.

Therefore, entering Mode 3 due to placing more cooling online is not a concern.

C is incorrect: Plausible because boron plateout is a concern when a high boron concentration solution contacts a heat source. However, the RH Hx is a source of cooling.

D is incorrect: Plausible because it is the opposite of the correct answer.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q31 User ID BRDLC3CRH3005 System ID 2169385 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.1 Fundamentals of reactor theory, including fission process, 10CFR55 Content neutron multiplication, source effects, control rod effects, criticality indications, reactivity coefficients, and poison effects.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BOP RH-6, Rev.52 Training Objective S.RH1-09-A Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of operational implication of RHRS dilution considerations.

SRO-Only Justification N/A Additional Information From Byron LOR bank K/A Reference(s)

SF4.005.K5.09 Safety Function 4 Tier 2 Group 1 RO Imp: 3.2 SRO Imp: 3.4 Knowledge of the operational implications of the following concepts as they apply the RHRS: (CFR: 41.5 / 45.7)

Dilution and boration considerations Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 84 of 229

2021 RO/SRO NRC Exam Test Key Question 32 ID: 2169386 Points: 1.00

An automatic reactor trip and SI occurred on Unit 1 from 100% power.

1CV112D, RWST TO CHG PMPS SUCT VLV, is stuck CLOSED and will not open.

What is the result of this failure to the high head ECCS suction source?

A. Suction will be from VCT ONLY.

B. Suction will be from RWST AND VCT.

C. Suction will be from RWST with 1CV112B, VCT OUTL ISOL VLV, OPEN and 1CV112C, VCT OUTL ISOL VLV, CLOSED.

D. Suction will be from RWST with 1CV112B, VCT OUTL ISOL VLV, CLOSED, and 1CV112C, VCT OUTL ISOL VLV, CLOSED.

Answer C Answer Explanation A - Incorrect: Would be correct if the parallel and series valve configurations were reversed, which is a plausible misconception.

B - Incorrect: Would be correct if both suction sources were parallel, which is a plausible misconception.

C - Correct: The RWST suction line isolation valve, 1CV112D/E are configured on parallel lines. The VCT suction valves, 1CV112B/C are configured in series on a single line. 1CV112D/E open from a direct SI actuation signal. The VCT outlet valves are interlocked by independent trains such that 1CV112B closes when 1CV112D is full open and 1CV112C closes when 1CV112E opens. Therefore, a failure of 1CV112D to open would prevent 1CV112B from closing. However, the high head suction would be from the RWST only because the RWST suction lines and valves are in parallel and the VCT suction valves are in series.

D - Incorrect: Would be correct if 1CV112B/C both received a close signal direct from SI actuation, which is a plausible misconception.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q32 User ID RS10006-N05 System ID 2169386 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 6E-1-4030CV10, Rev. O Training Objective S.CV1-16-H Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the effect of a malfunction with borated water source on ECCS.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF2.006.K6.01 Safety Function 2 Tier 2 Group 1 RO Imp: 3.4 SRO Imp: 3.9 Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: (CFR: 41.7 / 45.7)

BIT/borated water sources Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 86 of 229

2021 RO/SRO NRC Exam Test Key Question 33 ID: 2202792 Points: 1.00

Unit 1 is in MODE 4, 275°F RCS temperature, 300 psig.

RCS boron concentration is 1980 ppm.

Plant heatup is in progress following a refuel outage.

ALL RCPs are available.

ONLY 1D RCP is running.

1A RH train is running in shutdown cooling.

1B RH train is aligned for cold leg injection.

1D NR SG level is 25%.

1A, B & C NR SG levels are all approx. 50%.

Preparations to start 1C RCP per BOP RC-1, STARTUP OF A RCP, are in progress.

The 1A RH train is being secured from S/D cooling and re-aligning it for injection per BOP RH-11, SECURING THE RH SYSTEM FROM SHUTDOWN COOLING.

Prior to entering MODE 3, what must be done to ensure the Tech Spec 3.5.2, ECCS-OPERATING, requirements are met?

A. One additional RCP MUST be in operation.

B. 1D SG level MUST be raised.

C. 1A RH train boron concentration MUST be raised.

D. 1A RH train temperature MUST be lowered.

Answer D Answer Explanation A is incorrect, Plausible because T.S 3.4.6 "RCS Loops- MODE 4" requires two loops of RC or RH operable but only one in operation. The 1D RCP running satisfies the loop in operation and the standby RCS loops satisfy the second operable loops.

B is incorrect, LCO 3.4.6 only requires 1 RCS loop to be in operation in MODE 4. Plausible because TS 3.4.6 only requires >=18% NR level for the RCS loop in operation in MODE 4. This is plausible since SG NR level is normally maintained at 60% +/- 5% at power.

C is incorrect, There is no requirement for the 1A RH train to be borated prior to aligning for injection.

MODE 4 only requires one ECCS train which is satisfied by the 1B RH train. This is plausible since there is a requirement to ensure the RH train is borated to the COLR limit in the alignment for shutdown cooling procedure BOP RH-6. However, that is not a requirement for securing from shutdown cooling.

D is correct, Per BOP RH-11, Isolating an RH suction from the RCS with RCS Hot Leg temperature >

200°F will render the associated RH Train inoperable for ECCS Cold Leg Injection until the RH Pump suction is < 200°F.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q33 User ID RS10005-C01 System ID 2202792 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 10CFR55 Content CFR: 41.8 Components, capacity, and functions of emergency systems.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BOP RH-11 Rev. 30, Limitation and action E.6 Training Objective S.RH1-09-A Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict changes to avoid exceeding design limits of RH system temperature when aligning the system for ECCS injection.

SRO-Only Justification N/A Additional Information From Bwd 2020 NRC exam K/A Reference(s)

SF2.006.A1.12 Safety Function 2 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 ECCS controls including: (CFR: 41.5/45.5)

RHR heatup limits Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 88 of 229

2021 RO/SRO NRC Exam Test Key Question 34 ID: 2169388 Points: 1.00

Unit 2 is at 100% power.

Annunciator 2-12-B7, PRT PRESS HIGH, is in alarm.

PRT Level: 74%

PRT Temp: 80°F

PRT Press: 10 psig

2RY469, PRT TO GW ISOLATION VALVE, indicates CLOSED.

To REDUCE PRT pressure to 3 psig, what actions are required?

A. Vent ONLY.

B. Vent, THEN Drain.

C. Drain, THEN Vent.

D. INITIALLY Vent and Drain SIMULTANEOUSLY.

Answer C Answer Explanation A. Incorrect: The vent valve will not open at 10 psig. It is plausible as normally vent valves do not have pressure interlocks to auto close.

B. Incorrect: The evolutions stated are correct, but they are in the wrong order as described above making this distractor plausible.

C. Correct: Per the Alarm Response Procedure the PRT vent valve auto closes at a pressure of 6 psig.

Once this valve closes, the only way to reduce pressure in the PRT is to lower level. This is accomplished by utilizing BOP RY-4, DRAINING THE PRESSURIZER RELIEF TANK. Draining the PRT will reduce pressure which would then allow the tank to be vented once pressure is less than 6 psig. Level will first be lowered to reduce pressure to <6 psig, then the vent valve can be opened to reduce pressure to the normal setpoint of approximately 3 psig.

D. Incorrect: This distractor is plausible as it contains the actions necessary to reduce pressure; however, they cannot be performed simultaneously because the pressure is too high to allow opening the vent valve.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q34 User ID 2017 NRC Q75A System ID 2169388 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BAR 1-12-B7, Rev. 53 BAR 1-12-A7, Rev. 5BOP RY-4, Rev. 8 Training Objective S.RY1-17 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict changes associated with operating PRT system controls for maintaining PRT pressure.

SRO-Only Justification N/A Additional Information From 2017 Byron NRC exam K/A Reference(s)

SF5.007.A1.02 Safety Function 5 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 PRTS controls including: (CFR: 41.5/45.5)

Maintaining quench tank pressure Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 90 of 229

2021 RO/SRO NRC Exam Test Key Question 35 ID: 2202822 Points: 1.00

A localized instrument air (IA) leak required isolating IA to 1CC182, CC SURGE TK PRI WTR MU VLV, and 1CC183, CC SURGE TK DEMIN WTR MU VLV.

No other valves are affected.

What will result from the IA loss?

A. BOTH 1CC182 AND 1CC183 will fail CLOSED.

B. 1CC182 will fail CLOSED. 1CC183 will fail OPEN and WM will need to be locally isolated to the CC Surge Tank.

C. 1CC182 will fail OPEN and PW will need to be locally isolated to the CC Surge Tank. 1CC183 will fail CLOSED.

D. BOTH 1CC182 AND 1CC183 will fail OPEN. PW AND WM will need to be locally isolated to the CC Surge Tank.

Answer B Answer Explanation A is incorrect, 1CC183 will fail open. Plausible because 1CC182 fails closed.

B is correct, 1CC182 will fail CLOSED. 1CC183 will fail OPEN. The local isolation of the failed open air operated valve could be administratively controlled with a with an EST tag. If the crew chose to use OA procedural guidance for the CC system malfunction, 1BOA PRI-6 would direct the local isolation of the failed open valve.

C is incorrect, Plausible because it is opposite of the correct answer.

D is incorrect, 1CC182 will fail closed. Plausible because 1CC183 fails open.

Question Information Topic 2021 NRC Q35 User ID RS10008-N05 System ID 2202822 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 10CFR55 Content CFR: 41.8 Components, capacity, and functions of emergency systems.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type New Difficulty Technical Reference and Revision # M-66 Sht. 4A Training Objective S.CC1-18 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to predict the impact of loss of IA on a CC system AOV and use procedures to mitigate the malfunction.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF8.008.A2.05 Safety Function 8 Tier 2 Group 1 RO Imp: 3.3* SRO Imp: 3.5 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, con- trol, or mitigate the consequences of those malfunc- tions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

Effect of loss of instrument and control air on the position of the CCW valves that are air operated Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 92 of 229

2021 RO/SRO NRC Exam Test Key Question 36 ID: 2169390 Points: 1.00

Unit 1 is at 100% power.

1PK-455A, PZR MASTER PRESSURE CONTROLLER, demand is at 26% in AUTOMATIC.

While preparing for a ramp down, the Unit 1 NSO placed two sets of PZR backup heaters ON.

Ten minutes after energizing the PZR backup heaters, which of the following indications would be present on 1PM05J?

A. 1PK-455B, PZR SPRAY VALVE CONTROLLER, demand has RISEN.

B. PZR Variable Heater current has RISEN.

C. 1RY455A, PZR PORV, open and closed lights BOTH LIT.

D. 1PK-455A, PZR MASTER PRESSURE CONTROLLER, demand has DROPPED.

Answer A Answer Explanation A is correct, When PZR backup heaters are energized, PZR pressure rises and variable heater demand will lower to 0%. Rising PZR pressure will cause demand on the PZR master controller to rise. PZR spray valves will open and remain open to lower RCS pressure back to 2235 psig. PZR PORVs will remain closed. PZR master pressure controller will stabilize at a higher value.

B is incorrect, Plausible because variable heater demand will change. However, demand would lower to 0 amps.

C is incorrect, Plausible because pressurizer pressure will rise. However, PORVs will not open.

D is incorrect, Plausible because master pressure controller demand will change. However, demand will rise above 26%.

Question Information Topic 2021 NRC Q36 User ID RS10010-C01 System ID 2169390 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BOP RY-9, Rev. 12, I1-RY-XL-01 Pressurizer LP rev. 8, page 26 Training Objective S.RY1-08-B Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to analyze and determine Pzr pressure response to manual operation of the Pzr PCS (heaters) and apply to Pzr pressure control system response.

SRO-Only Justification N/A Additional Information From Bwd 2011 Cert exam K/A Reference(s)

SF3.010.A3.02 Safety Function 3 Tier 2 Group 1 RO Imp: 3.6 SRO Imp: 3.5 Ability to monitor automatic operation of the PZR PCS, including: (CFR: 41.7 / 45.5)

PZR pressure Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 94 of 229

2021 RO/SRO NRC Exam Test Key Question 37 ID: 2169391 Points: 1.00

Unit 1 is at 100% power.

Pressurizer pressure channel 1PT-455 is in test (all required bistables TRIPPED).

Subsequently, pressurizer pressure transmitter 1PT-458 fails LOW causing a low pressurizer pressure SI.

Five minutes later, the crew has transitioned to 1BEP ES-1.1, SI TERMINATION.

The NSO depresses BOTH SI RESET pushbuttons.

The BYPASS - PERMISSIVE LIGHTS silence, acknowledge, and reset pushbuttons are depressed.

Which of the following BYPASS - PERMISSIVE LIGHTS will be LIT?

A. SI ACTUATED B. AUTO SI BLOCKED C. PZR SI BLOCKED TRN A D. PZR LOW PRESS SI BLOCK PERMISSIVE P11 Answer B Answer Explanation A is incorrect, SI ACTUATED will go dark after reset pushbuttons are depressed and AUTO SI BLOCKED will light. This prevents further automatic SI signals from actuating. Manual SI will still re-actuate SI even with SI blocked. The condition that caused the initial SI is still present, making this a plausible distractor.

B is correct, resetting SI later than 1 minute after an auto SI will block auto SI and light the AUTO SI BLOCKED alarm.

C is incorrect, this alarm lights when pressure is <P-11 and the SI lo press SI block switch is taken to block. This is plausible since the PZR SI signal is auto blocked from actuating SI once the SI reset buttons are pressed.

D is incorrect, channel 458 does not input into the 2/3 logic for P-11. P-11 will light when 2 of 3 pressurizer pressure channels are below 1930 psig, making this a plausible distractor.

Test ID: 347808 09/15/2021 95 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q37 User ID RE1WE02-N01 System ID 2169391 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BAR 1-BP-5.1, Rev. 0 Training Objective 3D.EP-02-E Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor actuation of reset switches associated with the RPS.

SRO-Only Justification N/A Additional Information From Bwd 2018 NRC exam K/A Reference(s)

SF7.012.A4.04 Safety Function 7 Tier 2 Group 1 RO Imp: 3.3* SRO Imp: 3.3 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)

Bistable, trips, reset and test switches Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 38 ID: 2203915 Points: 1.00 Unit 1 has had a reactor trip and SI from 100% power.

The RO is currently performing 1BEP-0, REACTOR TRIP OR SI, Attachment B, step 4.a, GROUP 2 RCFC ACCIDENT MODE STATUS LIGHTS - LIT.

ONE of the FOUR RCFC Accident Mode Status Lights is NOT LIT.

Which SINGLE action will cause the dark RCFC Accident Mode Status Light to LIGHT?

A. OPEN an RCFC Inlet Isolation Valve at 1PM06J.

B. START an RCFC in LOW speed at 1PM06J.

C. OPEN an SX Containment Chiller Bypass Valve at 0PM02J.

D. CLOSE an SX Containment Chiller Isolation Valve 0PM02J.

Answer B Answer Explanation A - Plausible: This would be correct if 2 RCFC accident mode lights were not lit.

B - Correct: The RCFC accident mode lights have inputs from 5 separate valves limit switches and the RCFC fan low speed breaker auxiliary contacts. All of the valve limit switches feed two individual lights, while the RCFC breaker contacts are specific to each light. Therefore, if only one light is not lit, the component that is specific to the individual light is the RCFC. See electrical contact diagram below.

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2021 RO/SRO NRC Exam Test Key C - Plausible: This would be correct if 2 RCFC accident mode lights were not lit.

D - Plausible: This would be correct if 2 RCFC accident mode lights were not lit.

Question Information Topic 2021 NRC Q38 User ID RS20022-N04 System ID 2203915 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Test ID: 347808 09/15/2021 98 of 229

2021 RO/SRO NRC Exam Test Key Technical Reference and Revision # 6E-1-4030AN057 Rev. H Training Objective S.VP1-06 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to locate indication lights and control switches to determine correct lineup for Containment Cooling SI alignment.

SRO-Only Justification N/A Additional Information From Bwd 2016 NRC exam K/A Reference(s)

GS.3.0.SF2.013 Safety Function 2 Tier 2 Group 1 RO Imp: SRO Imp:

Engineered Safety Features Actuation System (ESFAS)

P2.1.31 Safety Function 2 Tier 3 Group RO Imp: 4.6 SRO Imp: 4.3 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

(CFR: 41.10 / 45.12)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 39 ID: 2169393 Points: 1.00

Unit 1 is at 100% power.

1A & 1C RCFCs are NOT running.

1SX016A/1SX027A, 1A RCFC SX Inlet/Outlet Valves, are CLOSED.

A reactor trip and SI then actuate.

What is the expected SEQUENCE of operation of the following valves and RCFCs?

A. 1SX027A opens, 1A/1C low speed RCFCs start, then 1SX016A opens.

B. 1SX027A opens, 1SX016A opens, then 1A/1C low speed RCFCs start.

C. 1SX016A opens, 1A/1C low speed RCFCs start, then 1SX027A opens.

D. 1SX016A opens, 1SX027A opens, then 1A/1C low speed RCFCs start.

Answer C Answer Explanation A - Incorrect: Order of SX inlet and outlet valves opening are reversed. Plausible because the normal method of unisolating a pressurized system equipment is to open the outlet valve first.

B - Incorrect: Order of SX inlet and outlet valves opening are reversed and RCFC fan starting is listed last. Plausible because the normal method of unisolating a pressurized system equipment is to open the outlet valve first. Also, plausible because the starting of the RCFC fans is after the cooling system is aligned which would be the normal sequence to manually align and start the RCFC cooling system.

C - Correct: 1SX016A will open on the SI signal. The 1A and 1C RCFCs will receive start signals (for low speed) from the SI signal. After either the 1A or 1C RCFC start in low speed, 1SX027A receives a signal to open.

D - Incorrect: RCFC fan starting is listed last. Plausible because the starting of the RCFC fans is after the cooling system is aligned which would be the normal sequence to manually align and start the RCFC cooling system.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q39 User ID BYLC3CVP06D005 System ID 2169393 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 6E-1/2-4030SX10, Rev. I/F, 6E-1/2-4030SX11, Rev I/F, 6E-1/2-4030VP01, Rev. S/M, 6E-1/2-4030VP05, Rev. U/N, BOP VP-5, Rev. 4 Training Objective S.SX1-07-A, S.VP1-06 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of cause effect relationship between the RCFCs and SX valves.

SRO-Only Justification N/A Additional Information From Byron LOR bank K/A Reference(s)

SF5.022.K1.01 Safety Function 5 Tier 2 Group 1 RO Imp: 3.5 SRO Imp: 3.7 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

SWS/cooling system Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 40 ID: 2169394 Points: 1.00

A steam break inside containment occurred on Unit 1 from 100% power.

A Reactor trip and SI actuated.

Due to a containment cooling malfunction, containment pressure and temperature have risen quickly and containment is ADVERSE.

The crew is performing the appropriate EOPs for the event.

Which of the following will give an INACCURATE HIGH indication during the performance of the emergency procedures?

A. SG pressure B. Pressurizer level C. Containment pressure D. RCS wide range temperature Answer B Answer Explanation A - Incorrect: The SG pressure transmitters are located outside containment and therefore will not be adversely affected by higher containment temperature. Plausible because SG level transmitters are inside containment and can easily be confused with the pressure transmitters.

B - Correct: Reference leg heating of the pressurizer level system will result in less dense water in the reference leg and a smaller DP between the reference leg and the pressurizer vessel. Therefore, the indicated level will be inaccurately high. Thus, EOPs contain adverse containment setpoints for pressurizer level that are higher than normal containment setpoints. The adverse containment instrument inaccuracies are based on elevated containment temperature. But the criteria used to determine adverse containment conditions is containment pressure, because containment pressure is more readily available to the operators.

C - Incorrect: The containment pressure transmitters are located outside containment and therefore will not be adversely affected by higher containment temperature. Plausible because it is instrumentation sensing pressure inside containment.

D - Incorrect: Plausible because it is instrumentation inside containment. The RCS RTDs are installed in temperature element wells within the RCS piping are largely shielded from containment atmosphere.

They are designed for accurate readings well above the accident design pressure and temperature of containment atmosphere.

Test ID: 347808 09/15/2021 102 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q40 User ID RS10022-N04 System ID 2169394 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 1BEP-2, Rev. 300 Training Objective T.EP03-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the effect of high containment temperature on containment instrumentation.

SRO-Only Justification N/A Additional Information From Byron LOR bank K/A Reference(s)

SF5.022.K3.02 Safety Function 5 Tier 2 Group 1 RO Imp: 3.0 SRO Imp: 3.3 Knowledge of the effect that a loss or malfunction of the CCS will have on the following: (CFR: 41.7 / 45.6)

Containment instrumentation readings Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 41 ID: 2169395 Points: 1.00

Unit 1 was at 100% power.

An overcurrent relay problem has caused breaker 1415X, BUS 141 FEED TO XFMR 131X, to trip open and Bus 131X CANNOT be reenergized.

The following subsequently occurred:

An RCS LOCA.

Containment pressure is 26 psig.

The crew has just completed the Immediate Actions steps of 1BEP-0, REACTOR TRIP OR SAFETY INJECTION.

NO other operator actions have been taken.

What is the status of the 1A CS pump?

A. NOT running and CANNOT be started from the MCR.

B. NOT running but CAN be started from the MCR.

C. RUNNING and IS pumping water into containment.

D. RUNNING but NOT pumping water into containment.

Answer A Answer Explanation A - Correct: Bus 131X is the 480 volt (parent) feed to the 1A train of CS system MOVs. With Bus 131X de-energized, the 1A CS pump will not start automatically or manually because the valve interlocks are not made up. 1CS019A must be open for an auto start and 1SI8811A must be open for a manual start.

Both valves are normally closed and will not have power to open.

B - Plausible: Would be correct if 1SI8811A had power to open.

C - Plausible: Would be correct if 1CS019A and 1CS007A had power to open.

D - Plausible: Would be correct if 1CS019A had power to open.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q41 User ID RS20026-N05 System ID 2169395 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 6E-1-4030CS01, Rev. W, 6E-1-4030CS06, Rev. M, 6E-1-4030SI14, Rev. Q Training Objective S.CS1-08-D Previous Exam Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of bus power supply to the CSS MOVs.

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam K/A Reference(s)

SF5.026.K2.02 Safety Function 5 Tier 2 Group 1 RO Imp: 2.7* SRO Imp: 2.9 Knowledge of bus power supplies to the following: (CFR: 41.7)

MOVs Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 42 ID: 2169396 Points: 1.00

Unit 1 is at 80% power.

BOTH turbine driven feedwater pumps are in Auto.

The following occurs.

1MS072A, FW PUMP 1B HOT REHEAT STEAM SUPPLY ISOL VALVE, valve disk separates from the stem and BLOCKS steam flow.

What will be the effect on the 1B FW pump?

A. Will trip.

B. Will swap to SPEED SETTER control and maximum feedwater flow capability will drop to approximately 50%.

C. Will remain in AUTO SETPOINT control and maximum feedwater flow capability will drop to approximately 50%.

D. Will remain in AUTO SETPOINT control and maximum feedwater flow capability will remain approximately the same.

Answer D Answer Explanation A is incorrect: The TDFP will still supply feedwater; the examinee may consider a loss of steam supply as a trip. Plausible because an auto trip of the TDFW pumps is LP and HP stop valves being closed.

B is incorrect: The high pressure steam supply (main steam) will automatically open on lowering pump speed and will run the 1B TDFP at 100% capacity. Plausible because the TDFW pumps are operated in SPEED SETTER control with speed <3200 rpm.

C is incorrect: The high pressure governor valve will open, supplying the 1B TDFP from main steam.

Plausible because the TDFW pump has lost 1 of 2 steam supplies.

D is correct: The TDFP supplies are manually opened when starting up, but when on line, the HP governor valve will respond automatically. The high pressure steam supply (main steam) will automatically open on lowering pump speed and will run the 1B TDFP at 100% capacity.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q42 User ID RS10039-N04 System ID 2169396 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BOP FW-1, Rev. 23M-35 sheet 1, Rev AX N-BY-TQ-ILT-FW-37B, Main FW Pump Speed Control LP, Rev.5 section II.A.4 GV Operations Training Objective S.MS1-19 Previous 2 Byron NRC Exams Use 2019-1 References Provided None K/A Justification Question meets the K/A, requires examinee evaluate the failure of a steam supply to the MFW pump turbine and know the expected response.

SRO-Only Justification N/A Additional Information Question revised from previous NRC exam use.

Answers are similar but not different enough to be designated as modified.

K/A Reference(s)

SF4.039.K3.04 Safety Function 4 Tier 2 Group 1 RO Imp: 2.5* SRO Imp: 2.6*

Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: (CFR: 41.7 / 45.6)

MFW pumps Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 43 ID: 2169397 Points: 1.00 BOTH Units are at 100% power.

Which of the following conditions WOULD automatically trip a TDFW Pump on UNIT 2, but would NOT cause an automatic TDFW Pump trip on UNIT 1?

A. A P-4 and coincident Low Tave signal.

B. S/G level in ONE S/G DROPS to 20%.

C. S/G level in ONE S/G RISES to 85%.

D. S/G pressure in ONE S/G DROPS to 600 psig.

Answer C Answer Explanation A - Plausible: P-4 and coincident Low Tave signal causes a FWI on both units but not a TDFW pump trip on either unit.

B - Plausible: SG level dropping to 20% would cause a LO-2 SG level on unit 2 (setpoint is 36.3%) but not on Unit 1 (setpoint is 18%). However, a LO-2 SG level causes a reactor trip but not a TDFW pump trip.

C - Correct: SG level rising to 85% would cause a P-14 HI-2 SG level on unit 2 (setpoint is 80.8%) but not on Unit 1 (setpoint is 88%). P-14 directly causes a TDFW pump trip.

D - Plausible: SG pressure dropping to 600 psig would cause an SI signal on both units (both setpoints are 640 psig) and trip the TDFW pumps on both units.

Question Information Topic 2021 NRC Q43 User ID RS10059-N01 System ID 2169397 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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: 347808 09/15/2021 108 of 229

2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BAR 1-15-A8, Rev.6, BAR 2-15-A8, Rev. 5 Training Objective S.FW1-09 Previous Exam Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge interlocks which provide for MFW pump trips.

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam K/A Reference(s)

SF4.059.K4.16 Safety Function 4 Tier 2 Group 1 RO Imp: 3.1* SRO Imp: 3.2*

Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

Automatic trips for MFW pumps Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 44 ID: 2169398 Points: 1.00

Unit 1 is at 100% power.

The 1A and 1B FW pumps are running.

A secondary transient causes FW pump suction pressure to DROP to 250 psig as indicated on 1PI-CB014, FW PP SUCT HDR PRESS.

How will this affect the running FW pumps?

A. BOTH FW Pumps will TRIP.

B. BOTH FW Pumps will remain RUNNING.

C. 1A FW Pump will TRIP.

1B FW Pump will remain RUNNING.

D. 1A FW Pump will remain RUNNING.

1B FW Pump will TRIP.

Answer C Answer Explanation A - Incorrect: Plausible because the condition will trip the turbine driven feedwater pumps.Incorrect: The 1A FW pump will trip.

B - Plausible because if both turbine driven FW pumps were running this would be correct.

C - Correct: The 1A motor driven pump will trip on low suction pressure < 282 psig. No low suction pressure exists for the 1B turbine driven FW pump.

D - Incorrect: Opposite of correct answer. Plausible because a Low NPSH signal alarm will also likely come in. This alarm is a red annunciator on the MCB similar to the FW pump trip annunciators. However, the automatic actions from low NPSH are actions in the CD/CB system to raise FW pump NPSH, but not trip a FW pump.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q44 User ID RS10059-N05 System ID 2169398 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # BAR 1-16-A1 Rev. 3, BAR 1-16-B1, Rev. 5 Training Objective S.FW1-09, S.FW1-13 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to automatic response of low feedwater pump suction pressure.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF4.059.A3.03 Safety Function 4 Tier 2 Group 1 RO Imp: 2.5 SRO Imp: 2.6*

Ability to monitor automatic operation of the MFW, including:(CFR: 41.7 / 45.5)

Feedwater pump suction flow pressure Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 45 ID: 2202861 Points: 1.00

Unit 2 is at 50% power.

The 2B AF Pump was shutdown 30 minutes ago following a monthly surveillance run.

The EO performing field operations reports that the 2B AF Pump discharge piping is 150°F and has risen since the pump was secured.

1. What procedure's mitigation strategy will be used for this event?

2. Will the performance of the appropriate BOA require a Tech Spec entry for the 2B AF system?

A. 1. 2BOA SEC-6, LOSS OF FEEDWATER TEMPERING LINE SUBCOOLING

2. NO B. 1. 2BOA SEC-7, AUXILIARY FEEDWATER CHECK VALVE LEAKAGE

2. NO C. 1. 2BOA SEC-6, LOSS OF FEEDWATER TEMPERING LINE SUBCOOLING

2. YES D. 1. 2BOA SEC-7, AUXILIARY FEEDWATER CHECK VALVE LEAKAGE 2 YES Answer D Answer Explanation A is incorrect, The plausible distractor for this question are FW tempering flow nozzle shock and 2BOA SEC-6. This concern and procedure will be entered when low flow is detected in the tempering line which the AF header combines with just prior to entering the S/Gs. No TS entry is plausible because closing the upstream isolation (2AF004B) for the 2AF013A/B/C/D valves does not require a TS entry because the 2AF004B has a auto opening interlock for auto AF pump starts.

B is incorrect, With AF discharge line temperature at 150°F, 2BOA SEC-7 is going to require the respective 2AF013_ valves to be closed and the AF piping to cool. Closing the 2AF013_ valves requires a TS 3.7.5 entry per a note in 2BOA SEC-7, as it will not automatically be able to perform it's safety function.

C is incorrect, See distractor A explanation.

D is correct, Entry conditions for 2BOA SEC-7 is any AF line temperature greater than 130°F. The AF piping temperature will rise if back leakage through check valves from the MFW system is occurring. The major concern is temperature in the AF system rising to the level of steam binding and inoperability of an AF pump. With AF discharge line temperature at 150°F, 2BOA SEC-7 is going to require the respective 2AF013_ valves to be closed and the AF piping to cool. Closing the 2AF013_ valves requires a TS 3.7.5 entry per a note in 2BOA SEC-7, as it will not automatically be able to perform its safety function.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q45 User ID SS20061-N01 System ID 2202861 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 2BOA SEC-7 Rev. 104 Training Objective R-AF-007 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of operational implications of Aux Feed Water line voiding.

SRO-Only Justification N/A Additional Information From Bwd 2011 NRC exam K/A Reference(s)

SF4.061.K5.05 Safety Function 4 Tier 2 Group 1 RO Imp: 2.7 SRO Imp: 3.2 Knowledge of the operational implications of the following concepts as the apply to the AFW: (CFR: 41.5 / 45.7)

Feed line voiding and water hammer Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 46 ID: 2169400 Points: 1.00

Both Units were at 100% power.

A tornado swept through the switchyard causing a loss of offsite power.

BOTH reactors tripped.

Unit 2 experienced a loss of all AC power.

Bus 141 is now supplying bus 241.

The following indications have been present for the past 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

1JI-DG002 DIESEL GEN 1A OUTPUT WATTS: 6100 KW

1II-DG001 DIESEL GEN 1A OUTPUT CURRENT: 1010 AMPS

1II-AP053 BUS 241 FEED TO BUS 141 CURRENT: 930 AMPS What is the status of the DG load limitations?

A. NO limits are exceeded.

B. The limits on DG current AND bus crosstie current are exceeded.

C. The limits on DG watts AND bus crosstie current are exceeded.

D. The limits on DG watts AND output current are exceeded.

Answer C Answer Explanation A: Incorrect. Plausible because exceeded indications in question stem are only moderately above the DG limits.

B: Incorrect. Current is below the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limit. Plausible because these parameters have limits.

C: Correct. The limits on EDG Watts AND bus crosstie current are exceeded.

Per BOP DG-11 the DG limits are:

Continuous 5500 KW @ 954 amps 5500-5935 KW @ 1030 amps for up to 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months 5935-6050 KW @ 1050 amps for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period Per BCA-0.0 OAS the Power Source Capacity limit is:

925 amps Unit 2 reserve feed (cross-tie) cable limit D: Incorrect. Current is below the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limit. Plausible because these parameters have limits.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q46 User ID RS10064-N04 System ID 2169400 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BOP DG-11, Rev. 28 Training Objective 4C.DG-06 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor DG load limits.

SRO-Only Justification N/A Additional Information From Bwd 2013 NRC exam K/A Reference(s)

SF6.062.A1.01 Safety Function 6 Tier 2 Group 1 RO Imp: 3.4 SRO Imp: 3.8 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: (CFR: 41.5 / 45.5)

Significance of D/G load limits Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 47 ID: 2169401 Points: 1.00

The 1A DG was started per 1BOSR 8.1.2-1, UNIT ONE 1A DIESEL GENERATOR OPERABILITY SURVEILLANCE.

INCOMING VOLTAGE DIV 11 is 117 VAC.

RUNNING VOLTAGE DIV 11 is 120 VAC.

SYNCHROSCOPE DIV 11 is spinning SLOWLY in the FAST direction.

ACB 1413 was just CLOSED.

1. When ACB 1413 closed, what was the INITIAL reactive loads on the DG?

2. What actions should the RO take regarding reactive load?

A. 1. KILOVARS IN

2. LOWER DIESEL GEN 1A VOLT ADJ until reactive load is 0-1000 KV OUT.

B. 1. KILOVARS IN

2. RAISE DIESEL GEN 1A VOLT ADJ until reactive load is 0-1000 KV OUT.

C. 1. KILOVARS OUT

2. LOWER DIESEL GEN 1A VOLT ADJ until reactive load is 0-1000 KV IN.

D. 1. KILOVARS OUT

2. RAISE DIESEL GEN 1A VOLT ADJ until reactive load is 0-1000 KV IN.

Answer B Answer Explanation A - Incorrect: Lowering DG VOLT ADJ switch will cause reactive load to move further in the IN direction.

Plausible because adjustment in opposite direction is correct.

B - Correct: BOP DG-11 directs the DG to be run between 0 and 1000 KV OUT. The correct adjustment prior to paralleling the DG is incoming voltage (DG output voltage) slightly higher (0-4 volts) than running voltage (bus voltage). It is not intended to run a DG with KV IN, but with incoming volts misadjusted the initial reactive load will be KV IN. The DG VOLT ADJ switch must be moved in the raise direction to adjust KV to 0-1000 KV OUT.

C - Incorrect: Opposite the correct answer. Plausible because reactive load and adjustment in opposite direction are correct.

D - Incorrect: With incoming voltage less than running voltage KV will be IN. Plausible because reactive load in opposite direction is correct.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q47 User ID RS10062-N04 System ID 2169401 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BOSR 8.1.2-1, Rev. 35 Training Objective S.DG1-06-D Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict the consequences of paralleling DG with a mismatch in volts.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF6.062.A2.15 Safety Function 6 Tier 2 Group 1 RO Imp: 2.8 SRO Imp: 3.2 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)

Consequence of paralleling out-of-phase/mismatch in volts Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 48 ID: 2169402 Points: 1.00 Which of the following electrical busses supplies power to the 1TO05P, Main Turbine Emergency Oil Pump?

A. Bus 132X B. MCC 133Z2 C. DC Bus 111 D. DC Bus 123 Answer D Answer Explanation A is incorrect, but plausible because the 1TO06P Bearing Oil Pump is supplied by AC bus 132X.

B is incorrect, but plausible because MCC 133Z2 powers other turbine non-ESF loads including one of the Main Oil Pumps to the 1C Feedwater Pump.

C is incorrect, but plausible because the Main Turbine Emergency Oil Pump name implies it is an "emergency" load and DC bus 111 supplies multiple ESF or "emergency" loads.

D is correct, 1TO05P, Main Turbine Emergency Oil Pump is supplied by 250 VDC Bus 123. The 1TO05P is the second backup source of supplying oil to the main turbine in the event of a loss of normal supply by the main turbine shaft driven oil pump or the 1TO06P, Bearing Oil Pump (first backup).

Question Information Topic 2021 NRC Q48 User ID RS20063-N04 System ID 2169402 Status Active Point Value 1.00 Time (min) 1 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Test ID: 347808 09/15/2021 118 of 229

2021 RO/SRO NRC Exam Test Key Technical Reference and Revision # 6E-1-4030TO04 Rev. H Training Objective S.DC2-02 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the power supply to a major DC load, the Main Turbine Emergency Oil Pump.

SRO-Only Justification N/A Additional Information From Bwd 2016 NRC exam K/A Reference(s)

SF6.063.K2.01 Safety Function 6 Tier 2 Group 1 RO Imp: 2.9* SRO Imp: 3.1*

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

Major DC loads Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 49 ID: 2169403 Points: 1.00

Unit 1 was at 100% power.

A DC circuit ground causes a loss of 120 VDC control power (blown fuse) to Reactor Trip Breaker RTA.

1. If a reactor trip signal subsequently occurs, which RTA trip actuation device will NOT function?

2. What Tech Spec LCO is applicable?

A. 1. UV Coil

2. TS 3.3.1 Reactor Trip Instrumentation B. 1. UV Coil

2. TS 3.8.9 Distribution Systems Operating C. 1. Shunt Trip Coil

2. TS 3.3.1 Reactor Trip Instrumentation D. 1. Shunt Trip Coil

2. TS 3.8.9 Distribution Systems Operating Answer C Answer Explanation A - Incorrect: The UV coil for RTA is powered by 48 VDC from A train of SSPS and will continue to function with a loss of 120 VDC control power to RTA. The second part is correct. Plausible because the power supplies for the trip actuation devices are easily confused.

B - Incorrect: The UV coil for RTA is powered by 48 VDC from A train of SSPS. Procedure BOP DC 111, 111/113 Ground Detection, directs entry to TS 3.3.1 when de-energizing the RTA Shunt Trip device.

TS 3.8.9 bases states OPERABLE DC electrical power distribution subsystems require the associated buses to be energized to their proper voltage from either the associated battery or charger. Therefore, an individual control power circuit would require the specific affected equipment TS entry. TS 3.3.1 is applicable per Table 3.3.1-1, function 19, Reactor trip breaker UV and shunt trip mechanisms. Plausible because the power supplies for the trip actuation devices are easily confused.

C - Correct: The shunt trip coil is powered from 120 VDC. Procedure BOP DC-23-111, 111/113 Ground Detection, directs entry to TS 3.3.1 when de-energizing the RTA Shunt Trip device. TS 3.8.9 bases states OPERABLE DC electrical power distribution subsystems require the associated buses to be energized to their proper voltage from either the associated battery or charger. Therefore, an individual control power circuit would require the specific affected equipment TS entry. TS 3.3.1 is applicable per Table 3.3.1-1, function 19, Reactor trip breaker UV and shunt trip mechanisms.

D - Incorrect: The first part is correct. TS 3.8.9 bases states OPERABLE DC electrical power distribution subsystems require the associated buses to be energized to their proper voltage from either the associated battery or charger. Therefore, an individual control power circuit would not require the specific affected equipment TS entry. Plausible because the malfunction is a DC circuit.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q49 User ID RS10063-N05 System ID 2169403 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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.

CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 6E-1-4030RD06, Rev. U, BOP DC-23-111, Rev. 4, TS 3.3.1, Amendment 212 Training Objective S.RD1-21 Previous Exam Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict impact of a DC system ground and which procedure (BOL) will be used to control the malfunction.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF6.063.A2.01 Safety Function 6 Tier 2 Group 1 RO Imp: 2.5 SRO Imp: 3.2*

Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; 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)

Grounds Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 122 of 229

2021 RO/SRO NRC Exam Test Key Question 50 ID: 2201855 Points: 1.00

The 1A DG was in standby with the #1 Air Receiver and #1 Compressor OOS for maintenance.

1A DG was started per 1BOSR 8.1.2-1, UNIT ONE 1A DIESEL GENERATOR OPERABILITY SURVEILLANCE, for a normal monthly start.

The #2 Air Receiver relief valve stuck OPEN when the receiver was repressurizing.

Currently the #2 Air Receiver is blowing down and approaching 0 psig.

Which of the following 1A DG trips remain AVAILABLE?

A. Engine Overspeed B. Low Lube Oil Pressure C. Generator Differential Current D. Emergency Stop Push Button Answer A Answer Explanation A. Correct, on a loss of starting air pressure, the engine can operate without pneumatic protection/control air, but will not trip (except overspeed, which is a mechanical trip) on any automatic or manual signal. An overspeed signal will shut the air intake butterfly, which will stop the engine from a loss of combustion air.

B. Incorrect, the DG will not trip on low lube oil pressure. Pneumatic protection air is required to actuate the fuel control solenoid for all non-emergency trips. Plausible because the DG was stated for a non-emergency monthly run.

C. Incorrect, the DG will not trip on Generator Differential Current. Plausible because Generator Differential Current has a unique feature that will trip the DG output breaker after an auto start from SI.

D. Incorrect, the Emergency Stop Push Button will not trip the DG. Plausible because the Emergency stop push button is a local back up to non-emergency trips when the DG is running in emergency mode.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q50 User ID 2019 NRC-2 Q 51 System ID 2201855 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # 1BOSR 8.1.2-1 Rev. 35 Training Objective S.DG1-09-C Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee understand the effect the loss of an air receivers has on the emergency diesel generators.

SRO-Only Justification N/A Additional Information From Byron 2019 NRC-2 exam question 51.

K/A Reference(s)

SF6.064.K6.07 Safety Function 6 Tier 2 Group 1 RO Imp: 2.7 SRO Imp: 2.9 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 / 45.7)

Air receivers Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 51 ID: 2169405 Points: 1.00

The RM-23 for the 0PR032J, MCR OUTSIDE AIR INTAKE, monitor indicates the following:

Green AVAIL lights are NOT lit.

Amber INTLK lights are LIT.

Red HIGH lights are NOT lit.

What is the correct corresponding indication for the 0PR32J channels on the RMS Grid 2 Process Air Monitors screen?

A. WHITE, RMS Poll Status B. DARK BLUE, Operate Failure C. YELLOW, Channel Alert Alarm D. HALF INTENSITY CYAN (grey), Control Function Answer B Answer Explanation A - Incorrect: Plausible because the green available light is not lit. However, a Poll Status (monitor offline) condition will indicate all three lights not lit on the RM-23.

B - Correct: With only the amber light lit, the RM-23 is indicating an interlock or operate failure.

C - Incorrect: Plausible because the amber light is lit. However, a channel alert condition will also have the green light lit on the RM-23.

D - Incorrect: Plausible because a control function (check source test) failure would indicate on the RM-23 as described in the question stem. However, during the check source test, the RM-23 would indicate normal. (i.e. the green light lit, the amber and red lights not lit).

Question Information Topic 2021 NRC Q51 User ID BW-COPS3-065 System ID 2169405 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # BOP AR/PR-11A13, Rev. 52 Training Objective S.AR1-09 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor the RMS system in the MCR.

SRO-Only Justification N/A Additional Information From Bwd COPS exam bank K/A Reference(s)

SF7.073.A4.02 Safety Function 7 Tier 2 Group 1 RO Imp: 3.7 SRO Imp: 3.7 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)

Radiation monitoring system control panel Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 52 ID: 2169406 Points: 1.00 Which of the following signals will DIRECTLY cause _SX169A/B, DG _A/B SX VLV, to AUTOMATICALLY OPEN?

A. DG speed signal B. DG start signal C. Jacket water temperature signal D. DG output breaker closed Answer A Answer Explanation A is correct, The _SX169A/B valves open based upon a speed signal (>280 rpm) from the DG only.

Choice B is incorrect, but plausible because a start signal for the DGs actuates other support equipment.

Choice C is incorrect, but plausible because other cooling valves reposition on temperature feedback signal.

Choice D is incorrect, but plausible because other ESF functions are interlocked with the DG output breakers.

Question Information Topic 2021 NRC Q52 User ID RS10076-N01 System ID 2169406 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # 6E-1-4030SX17, Rev. M Training Objective S.SX1-09-D Test ID: 347808 09/15/2021 127 of 229

2021 RO/SRO NRC Exam Test Key Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor automatic operation of SWS isolation valve to DG by knowing when the valve will open.

SRO-Only Justification N/A Additional Information From Bwd 2011 NRC exam K/A Reference(s)

SF4.076.A3.02 Safety Function 4 Tier 2 Group 1 RO Imp: 3.7 SRO Imp: 3.7 Ability to monitor automatic operation of the SWS, including: (CFR: 41.7 / 45.5)

Emergency heat loads Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 53 ID: 2169407 Points: 1.00

Unit 1 experienced an event requiring MCR evacuation.

1BOA PRI-5, CONTROL ROOM INACCESSIBILITY, is in progress at the Remote Shutdown Panel (RSP).

The crew is aligning the 1A RH train for shutdown cooling to continue the plant cooldown to mode 5.

How will the 1RH606, RH 1A FLOW CONT VLV, be controlled during the plant cooldown?

A. At the RSP with a M/A station B. At the RSP with a control potentiometer C. Locally with a valve handwheel D. Locally with a pneumatic jumper Answer D Answer Explanation A - Incorrect: The RH flow control valves do not have controls at the RSP. Plausible because several other valves are controlled by a M/A Station at the RSP .

B - Incorrect: The RH flow control valves do not have controls at the RSP. Plausible because the 1RH606 is controlled in the MCR with a control potentiometer.

C - Incorrect: The 1RH606 does not have a valve handwheel. Plausible because 1IA065, the containment instrument air isolation valve is locally opened with a handwheel during performance of 1BOA ELEC-1.

D - Correct: Per 1BOA PRI-5, a pneumatic jumper is used to bypass the 1RH606 I/P converter.

Question Information Topic 2021 NRC Q53 User ID RS10078-N05 System ID 2169407 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BOA PRI-5, Rev. 111 Training Objective T.OA16-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to locally control instrument air signal to a valve.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

GS.3.0.SF8.078 Safety Function 8 Tier 2 Group 1 RO Imp: SRO Imp:

Instrument Air System (IAS)

P2.1.30 Safety Function 8 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) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 54 ID: 2169408 Points: 1.00

Unit 2 is in MODE 3 preparing for a reactor startup.

All Shutdown banks are withdrawn.

Redundant Steam Pressure instrumentation failures resulted in an inadvertent safety injection.

To restore normal containment cooling alignment (RCFCs to FAST and Containment Chillers supplying RCFCs), what are the MINIMUM operator actions that must be completed?

A. Reset SI ONLY.

B. Reset Phase A ONLY.

C. Reset SI, then reset Phase A.

D. Reset STM LINE SI, then reset SI, then reset Phase A.

Answer C Answer Explanation A is Incorrect. SI will reset even though the two steam pressure channels are failed low, so depressing the SI RESET pushbuttons will reset SI, However, this will not restore normal containment cooling because chill water isolation valves will not open. Plausible because distractor is partially correct.

B is Incorrect. Phase A can be reset even if SI has NOT been reset. The safety injection signal actuates phase A slave relays. This still will not restore normal containment cooling because RCFC fans will not return to fast speed with an active SI signal. Plausible because distractor is partially correct.

C is Correct. In order to restore normal containment cooling (RCFCs to fast or desired speed and containment chiller operation) phase A and SI must be reset.

D is Incorrect. The steam line low pressure SI does not need to be reset because resetting SI will provide an auto SI block signal to the steam line low pressure SI. Plausible because distractor is partially correct.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q54 User ID RS10103-N03 System ID 2169408 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 6E-1-4030WO05, Rev. J, 6E-1-4030VP02, Rev. T Training Objective S.EF1-06 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to determine the effect of the active safety injection signal (due to the two failed low steam pressure channels) on the ability to reset the SI signal and phase A, in order to restore normal containment cooling.

SRO-Only Justification N/A Additional Information 2013 Bwd NRC exam K/A Reference(s)

SF5.103.K1.08 Safety Function 5 Tier 2 Group 1 RO Imp: 3.6 SRO Imp: 3.8 Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

SIS, including action of safety injection reset Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Test ID: 347808 09/15/2021 133 of 229

2021 RO/SRO NRC Exam Test Key Question 55 ID: 2169409 Points: 1.00

Unit 1 was at 100% power.

An inadvertent Phase A Containment Isolation occurs on a SINGLE ESF train.

TEN MINUTES later, the crew is attempting to diagnose which train actuated.

NO other Phase A Containment Isolation valves have been manipulated.

Which of the following CLOSED valves would POSITIVELY confirm that the relay was a TRAIN B actuation?

A. 1CV8100, SEAL WTR RTRN CNMT ISOL VLV B. 1CV8112, SEAL WTR RTRN CNMT ISOL VLV C. 1CC685, CC FROM RC PUMPS THERM BARR ISOL VLV D. 1WO020A 1A + 1C CHILL WTR OUTLET CNMT ISOL VLV Answer B Answer Explanation A is incorrect, 1CV8100 is a motor operated valve that is operated by A train relay actuation. Additionally, 1BOA PRI-13 specifically uses this valve to determine if A train actuated.

B is correct, 1CV8112 is a motor operated valve that is operated by B train relay actuation only because it is on a containment penetration that has two isolation valves. Additionally, 1BOA PRI-13 specifically uses this valve to determine if B train actuated.

C is incorrect, although 1CC685 receives a phase B (NOT phase A, train B) CIS. Therefore, it is not positive indication of a B train actuation.

D is incorrect, 1WO020A is a motor operated valve that is operated by A train relay actuation.

Additionally, 1BOA PRI-13 specifically uses this valve to determine if A train actuated. Although this valve has an A train designator in the EPN, it is still a plausible distractor because the WO containment isolation valves have a cross train valve (1WO056A) that is labeled with an A train EPN but is actuated from B train of SSPS.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q55 User ID RS10103-N01 System ID 2169409 Status Active Point Value 1.00 Time (min) 1 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # 1BOA PRI-13, Rev. 104 Training Objective T.OA23-07 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability monitor ESF slave relay actuation from the MCR.

SRO-Only Justification N/A Additional Information From Bwd 2011 NRC K/A Reference(s)

SF5.103.A4.03 Safety Function 5 Tier 2 Group 1 RO Imp: 2.7* SRO Imp: 2.7*

Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)

ESF slave relays Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 56 ID: 2169410 Points: 1.00

A xenon free reactor startup is in progress on Unit 1 using control rods only.

The reactor is exactly critical in the intermediate range below P-6.

IR range SUR is 0 DPM.

Control Bank D (CBD) control rods are at 135 steps.

The US then directs the RO to establish a steady state Startup Rate of 0.5 DPM, raise power to approximately 10-3%, then level power for recording of critical data.

The RO withdraws CBD rods 10 steps and establishes the 0.5 DPM steady startup rate.

What additional actions will raise power to 10-3% and then maintain power stable?

A. Maintain CBD at 145 steps. When power reaches approx. 10-3%, negative reactivity from ITC (Isothermal Temperature Coefficient) will level power.

B. Periodically withdraw CBD as power rises to maintain the steady 0.5 DPM Startup Rate. When power reaches approx. 10-3%, insert CBD to approximately 145 steps to maintain power steady.

C. Maintain CBD at 145 steps. When power reaches approximately 10-3%, insert CBD to approximately 125 steps to maintain power steady.

D. Maintain CBD at 145 steps. When power reaches approximately 10-3%, insert CBD to approximately 135 steps to maintain power steady.

Answer D Answer Explanation A is incorrect, power will not level off at 10-3% like it would at reaching the POAH (plausible) because there is no negative reactivity feedback from ITC at 10-3%.

B is incorrect, rods will not need to be withdrawn more than 145 steps to maintain the 0.5 DPM startup rate once a steady state startup rate has been established (plausible during subcritical operations). Also, leaving rods at 145 steps will not steady power at 10-3% (power will continue to rise).

C is incorrect, inserting rods to 125 steps after reaching 10-3% will make the reactor subcritical and establish a negative startup rate instead of maintaining power at 10-3% (plausible if SUR was positive at 135 steps).

D is correct, With a xenon free start up in progress and the reactor exactly critical in the intermediate range, once a steady state startup rate has been established the reactor will maintain that startup rate until the point of adding heat is reached. However, 10-3% is well below the point of adding heat.

Therefore, the RO will have to manually stop the power rise by inserting control rods. Since the reactor was exactly critical with CBD at 135 steps prior to the power rise, the RO will need to return CBD to approx. 135 steps to maintain exactly critical conditions again and level power at 10-3%.

Text in red was provided during exam administration as a result of an applicants question.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q56 User ID RG20002-N01 System ID 2169410 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.1 Fundamentals of reactor theory, including fission process, 10CFR55 Content neutron multiplication, source effects, control rod effects, criticality indications, reactivity coefficients, and poison effects.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1BGP 100-2A1, Rev. 36 Training Objective 3C.RD-02-A Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of operational implications of CRDS and the affect on SUR.

SRO-Only Justification N/A Additional Information From Bwd 2011 NRC exam K/A Reference(s)

SF1.001.K5.47 Safety Function 1 Tier 2 Group 2 RO Imp: 2.9 SRO Imp: 3.4 Knowledge of the following operational implications as they apply to the CRDS: (CFR: 41.5/45.7)

Factors affecting SUR: b-eff, l, p Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 57 ID: 2169411 Points: 1.00

Unit 1 is at 75% power.

All systems are in auto at stable, steady state condition.

Then the following event occurs:

A charging flow control malfunction causes pressurizer level to rise.

The crew takes manual control of charging flow and stabilizes pressurizer level at 60%.

Compare STEADY STATE demand of 1PK-455A, MASTER PZR PRESS CONT, before the event to current conditions.

With current conditions, how will 1PK-455A demand stabilize?

A. HIGHER because of more pressurizer heater input.

B. LOWER because a smaller pressurizer bubble exists.

C. LOWER because spray flow is more effective.

D. The SAME because saturation pressure is the same.

Answer A Answer Explanation A is correct: At initial conditions of 75% power, program pressurizer level is 51.25%. A transient that raised level to 60% at the same power level will cause a >5% deviation in pressurizer level. This will automatically turn on all the back-up heaters and raise the heat input into the pressurizer. The backup heaters have a capacity of 1400 KWW vs. only 400 KW for the variable heaters. This rise in heat input will cause the master pressurizer pressure controller demand to rise, lowering variable heater demand and raising spray flow demand, to maintain the pressurizer at 2235 psig steady state condition.

B is incorrect: During the transient, the rising liquid level will compress the pressurizer bubble, raising system pressure. However, this will raise demand on the master pressure controller. Plausible because would be correct if controller was direct acting for variable heaters.

C is incorrect: Although spray may be slightly more effective with a smaller bubble, initial steady state conditions have zero spray flow (except for a small amount of bypass flow) also turning on the back up heaters significantly raises heat input and therefore demand for spray flow. Plausible because this would be correct if heater input was the same as initial conditions.

D is incorrect: Although saturation pressure is the same, the rise in heater input causes higher demand on the master pressurizer pressure controller to maintain the same saturation conditions. Plausible because distractor would be correct if back up heater interlock was not active.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q57 User ID RS10010-N01 System ID 2169411 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BAR 1-12-C3, Rev. 4, I1-RY-XL-01 Pressurizer LP rev. 8 Training Objective 4C.RY-09 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of relationship between the Pzr level and heater control circuit during a level malfunction.

SRO-Only Justification N/A Additional Information From 2011 Bwd NRC exam K/A Reference(s)

SF2.011.K6.03 Safety Function 2 Tier 2 Group 2 RO Imp: 2.9 SRO Imp: 3.3 Knowledge of the effect of a loss or malfunction on the following will have on the PZR LCS: (CFR: 41.7 / 45.7)

Relationship between PZR level and PZR heater control circuit Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 58 ID: 2169412 Points: 1.00

Unit 1 is at 100% power.

The most recent QPTR surveillance result determined quadrant N41 had the HIGHEST QPTR calculation.

Subsequently, the RO performs a calorimetric surveillance and adjusts the N41 GAIN potentiometer slightly in the positive direction.

Percent Full Power indication slightly RISES.

Detector current indication remains the SAME.

What effect, if any, will the N41 gain adjustment have on the QPTR calculation?

The QPTR calculation will...

A. LOWER.

B. remain the SAME.

C. RISE and the other channels will LOWER.

D. RISE and the other channels will remain the SAME.

Answer B Answer Explanation A - Incorrect: Common misconception that gain adjustment affects detector current would make this plausible. Detector currents are only adjusted by maintenance calibrations of the NIs (not gain adjustment by the operators). Lower would be the opposite change of the misconception.

B - Correct: Adjusting the gain potentiometer on the PRNI drawer adjusts the drawer output (percent power indication) but does not affect the level of the detector current. Because QPTR is calculated using detector current, the gain adjustment will not affect the QPTR calculation.

C - Incorrect: Common misconception that gain adjustment affects detector current would make this plausible. Because QPRT calculations use the average of the normalized current, it is plausible that changing one detector output would affect the other channels.

D - Incorrect: Common misconception that gain adjustment affects detector current would make this plausible.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q58 User ID RS20015-N05 System ID 2169412 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BOSR 3.1.2-1, Rev.27, 1BOSR 2.4.1-1, Rev.16 Training Objective 4C.NI-05 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict impact of operating NI controls on QPTR.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF7.015.A1.04 Safety Function 7 Tier 2 Group 2 RO Imp: 3.5 SRO Imp: 3.7 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the NIS controls including: (CFR: 41.5. 45.5)

Quadrant power tilt ratio Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 59 ID: 2169413 Points: 1.00

The spent fuel pool level is approximately 24.5' as indicated on 0LI-FC001B, SFP LEVEL ABOVE T/RACK PRIMARY.

The crew has recently swapped FC cooling pumps to support maintenance.

The newly started FC cooling pump develops a LARGE LEAK between the pump and discharge check valve.

Spent Fuel Pool level is dropping.

1. With NO operator action, what is the approximate INDICATED water level that the Spent Fuel Pool will stabilize at?

2. After the leak is isolated, what will be the PREFERRED water source to refill the SFP?

A. 1. 4' - 5'

2. PW System B. 1. 4' - 5'

2. RWST C. 1. 17' - 18'

2. PW System D. 1. 17' - 18'

2. RWST Answer D Answer Explanation A is incorrect. Plausible because 4'-5' indicated is how far level would drop if both the transfer canal and cask fill area flooded from empty with 1FH001 open and Primary water is the normal make up source to the SFP when filling from evaporation loss.

B is incorrect. Plausible because 4'-5' indicated is the depth of the cooling water return lines were a break in the FC system downstream of the cooling pump discharge check valves siphon the pool.

C is incorrect. Plausible because Primary water is the normal make up source to the SFP when filling from evaporation loss.

D is correct. The suction piping of the FC cooling pumps is approx. 7' below the normal level (24.5') of the SFP. 24.5' - 7' = 17.5'. Per BOP FC-11, RWST is the normal makeup source per the referenced procedure. Additionally, BOP FC-11 contains a caution that reads "The PW system should only be used as a last resort makeup to the Spent Fuel Pool if level loss is due to system leakage. PW system can be used to makeup to the Spent Fuel Pool due to evaporation loses."

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q59 User ID RS20033-N02 System ID 2169413 Status Active Point Value 1.00 Time (min) 1 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # M-63 Sht. 1A, Rev. BI, BOP FC-11, Rev. 37 Training Objective S.FC1-05 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict impact of abnormal SFP water level loss and use procedure (BOP FC-11) to select proper refill water source.

SRO-Only Justification N/A Additional Information From 2016 Bwd NRC exam.

K/A Reference(s)

SF8.033.A2.03 Safety Function 8 Tier 2 Group 2 RO Imp: 3.1 SRO Imp: 3.5 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling 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)

Abnormal spent fuel pool water level or loss of water level Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 60 ID: 2203839 Points: 1.00 Which of the following prevents the New Fuel Elevator from inadvertently RAISING a spent fuel assembly?

A. Gripper closed interlock B. 100 mrem/hr radiation alarm interlock C. 1200 lbs weight interlock D. Limit switch sensing a fuel assembly Answer C Answer Explanation A - Incorrect: Plausible because the Refuel Machine fingers of the gripper mechanism locks in engaged or disengaged position unless the gripper tube exerts a downward force of 300 lbs.

B - Incorrect: Plausible because the Fuel Handling Building Bridge Crane has 0RE-AR039 which stops upward motion at 100 mrem/hr.

C - Correct: The weight of a fuel assembly will prohibit upward motion.

D - Incorrect: Plausible because the New Fuel Elevator also has a position limit switch interlock that prevent downward motion.

Question Information Topic 2021 NRC Q60 User ID RS20034-N02 System ID 2203839 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 New Difficulty Test ID: 347808 09/15/2021 144 of 229

2021 RO/SRO NRC Exam Test Key Technical Reference and Revision # OU-AP-203, Rev. 7 I1-FH-XL-01, Fuel Handling LP, Rev.5 Training Objective S.FH1-06-F Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor proper operation of the fuel handling equipment by knowing the load limit interlocks.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF8.034.A3.02 Safety Function 8 Tier 2 Group 2 RO Imp: 2.5* SRO Imp: 3.1 Ability to monitor automatic operation of the Fuel Handling System, including: (CFR: 41.7 / 45.5)

Load limits Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 61 ID: 2169415 Points: 1.00

Unit 1 is at 100% power.

A grid disturbance causes the main turbine to reach the overspeed protection circuit setpoint.

When the OPC 20-1 and 20-2 solenoid valves open, which Main Turbine valves will reposition closed to limit turbine speed?

A. Governor and intercept B. Throttle and intercept C. Governor and reheat stop D. Throttle and reheat stop Answer A Answer Explanation A is correct, When the OPC solenoids open on a turbine overspeed signal, the DEHC Aux Governor trip header will de-pressurize and throttle closed the governor and intercept valves until turbine speed drops below the setpoint. Then the OPC solenoids will de-energize and close. This will re-pressurize the aux governor header and reopen the GVs and IVs.

B is incorrect, a check valve in the emergency trip header prevents throttle valves from closing. Plausible because all four valve groups act as stop valves on a turbine trip and are controlled by DEHC system.

C is incorrect, a check valve in the emergency trip header prevents reheat stop valves from closing.

Plausible because all four valve groups act as stop valves on a turbine trip and are controlled by DEHC system.

D is incorrect, throttle and reheat stop valves do not close. Plausible because all four valve groups act as stop valves on a turbine trip and are controlled by DEHC system.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q61 User ID RS10039-N01 System ID 2169415 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # M-152 Sht. 2B, Rev F, M-152 Sht. 2C, Rev C Training Objective 3S.MS-01 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to monitor turbine stop valves. All four valve groups act as stop valves on a turbine trip. The reheat stop valves act as backups to the intercept valves.

SRO-Only Justification N/A Additional Information From 2011 Bwd NRC exam K/A Reference(s)

SF4.045.A4.06 Safety Function 4 Tier 2 Group 2 RO Imp: 2.8 SRO Imp: 2.7*

Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)

Turbine stop valves Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 62 ID: 2169416 Points: 1.00 Per 1BGP 100-3, POWER ASCENSION, Unit 1 Main Condenser Hotwell level control is realigned as power is raised.

Per 1BGP 100-3, POWER ASCENSION, the main condenser hotwell level controllers need to be aligned to the __ 1 __ indicated level as power is raised to __ 2 ___.

A. 1. LOWEST

2. Prevent tube flooding in the Main Condenser B. 1. LOWEST

2. Prevent cavitation of the CD pumps C. 1. HIGHEST

2. Prevent tube flooding in the Main Condenser D. 1. HIGHEST

2. Prevent cavitation of the CD pumps Answer B Answer Explanation A - Incorrect: Plausible because the interlock for normal and emergency overflow valves prevent hotwell overfill and tube flooding. However, the tube elevations are such that either level control channel will prevent tube flooding, regardless of the power level and alignment.

B - Correct: The basis for selecting hotwell level control is to control on the condenser side that is lower to ensure that the lowest hotwell level present in the condenser does not jeopardize NPSHA for the CD pumps.

C - Incorrect: Opposite controlling side. Plausible reason because the interlock for normal and emergency overflow valves prevent hotwell overfill and tube flooding.

D - Incorrect: Plausible because distractor is opposite controlling side.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q62 User ID RS20056-N01 System ID 2169416 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # 1BGP 100-3, Rev. 105, I1-CD-XL-01 Condensate/FW System LP Rev. 8, page 10 Training Objective S.CD2-02 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of condensate system function.

SRO-Only Justification N/A Additional Information From 2013 Bwd NRC exam K/A Reference(s)

GS.3.0.SF4.SEC.056 Safety Function 4 Tier 2 Group 2 RO Imp: SRO Imp:

Condensate System P2.1.27 Safety Function 4 Tier 3 Group RO Imp: 3.9 SRO Imp: 4.0 Knowledge of system purpose and/or function.

(CFR: 41.7)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 63 ID: 2169417 Points: 1.00 A release of the 0A Gas Decay Tank (GDT) is in progress per BCP 400-EWASTE GAS, GASEOUS EFFLUENT RELEASE FORM TYPE: WASTE GAY DECAY TANK.

Subsequently, the 0B (on line) GDT relief valve fails (sticks) open.

The rise in flow past 0PR02J, GDT EFFLUENT, rad monitor causes the skid to exceed the high radiation ALARM setpoint.

How will the above condition be mitigated?

Flow from...

A. the 0A GDT will be AUTOMATICALLY isolated, but flow from the 0B GDT can NOT be isolated.

B. BOTH the 0A and 0B GDT will be AUTOMATICALLY isolated.

C. the 0A GDT must be MANUALLY isolated, but flow from the 0B GDT can NOT be isolated.

D. BOTH the 0A and 0B GDT effluents must be MANUALLY isolated by CLOSING 0GW014, WASTE GAS DISCH VLV.

Answer A Answer Explanation A - Correct: The waste gas system is configured such that the relief valves discharge header intersects the waste gas release header upstream of 0PR02J rad monitor sample line. The rad monitor will detect the rise in flow and subsequent rise in radiation levels when the relief valve opens. However, the waste gas release valve 0GW014, is upstream of the relief valves intersection point. The high rad signal that will close 0GW014 to terminate the release from the 0A Tank, but will not isolate the flow from the 0B tank lifting release valve.

B - Incorrect: Plausible from a misconception of the system piping configuration.

C - Incorrect: Plausible as several other high rad alarms from rad monitors require manual actions to mitigate high rad conditions.

D - Incorrect: Plausible as several other high rad alarms from rad monitors require manual actions to mitigate high rad conditions.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q63 User ID RS20071-N01 System ID 2169417 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # M-69 Sht. 1 Rev. AJ Training Objective 3S.GW-01 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of interlocks for GDT isolation.

SRO-Only Justification N/A Additional Information 2013 Byron NRC exam K/A Reference(s)

SF9.071.K4.04 Safety Function 9 Tier 2 Group 2 RO Imp: 2.9 SRO Imp: 3.4 Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

Isolation of waste gas release tanks Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 64 ID: 2169418 Points: 1.00

Both units are at 90% power.

The following equipment is OOS.

1B CW Pump 0A WS Pump 1A SAC

All other equipment is normally aligned.

The following occurs:

Unit 1 reactor is manually tripped.

All equipment operates as designed.

ONE MINUTE LATER, bus 143 faults and is deenergized.

With the above conditions and NO operator actions, which of the following will occur?

A. Unit 1 PZR Backup Heater Group A energizes.

B. ALL Unit 1 steam dump valves close.

C. The standby-1 Station Air Compressor will auto start.

D. WS header pressure drops on BOTH units.

Answer B Answer Explanation A is incorrect, B/U heater group A is powered from bus 143, so the group will not energize. The distractor is plausible because if the non-ESF bus loss was 144, then the variable heater group on U-1 would loss power and the backup heaters on the energized bus would energize on low PZR pressure.

B is correct, A bus 143 fault will cause a loss of bus 143 and the 1A and 1C CW pumps breakers opening on UV. With the 1B CW pp previously OOS, C-9 interlock (ALL CW pp breakers open) would prevent steam dumps from arming and cause all steam dump valves to close.

C is incorrect, 1A SAC (which is OOS) is powered from bus 143, so the loss of bus 143 will not affect the status of instrument air. Plausible if the 1A SAC was running.

D is incorrect, 0A WS pump (which is OOS) is powered from bus 143, so the loss of bus 143 will not affect the status of WS. Plausible if the 0A WS pump was running.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q64 User ID RS20075-N01 System ID 2169418 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BAR 1-BP-5.6, Rev. 1, 6E-1-4030CW01 Rev. K, 6E-1-4030CW03 Rev. J Training Objective S.DU1-11 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of loss of CW system will have on ESFAS (C-9 interlock).

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam.

K/A Reference(s)

SF8.075.K3.07 Safety Function 8 Tier 2 Group 2 RO Imp: 3.4* SRO Imp: 3.5*

Knowledge of the effect that a loss or malfunctions of the circulating water system will have on the following: (CFR:

41.7 / 45.6)

ESFAS Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 65 ID: 2204570 Points: 1.00

The Station Air Compressors (SACs) are normally aligned per BOP SA-12, OPERATION OF SIERRA STATION AIR COMPRESSOR.

A leak has developed in the Instrument Air system.

Instrument Air and Station Air pressures are slowly dropping.

The LEAD and LAG SACs are both running.

How will the STANDBY 1 and STANDBY 2 SACs start?

Assume Station Air pressure continues to slowly drop.

A. NEITHER STANDBY SAC will auto start, and both MUST be manually started.

B. STANDBY 1 SAC will auto start, but STANDBY 2 SAC MUST be manually started from the MCR.

C. BOTH STANDBY SACs will auto start at the SAME setpoint.

D. BOTH STANDBY SACs will auto start at DIFFERENT setpoints.

Answer D Answer Explanation A - Incorrect: Plausible because not all standby redundant equipment has auto start features.

B - Incorrect: Plausible because the compressor configurations are programable by the compressor controller.

C - Incorrect: Plausible because the compressor configurations are programable by the compressor controller and both have the same offline pressure of 116 psig.

D - Correct: Per BOP SA-12, STANDBY 1 SAC has higher online pressure set point than STANDBY 2 SAC. Both have the same offline pressure of 116 psig.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q65 User ID RS20079-N03 System ID 2204570 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # BOP SA-12, Rev. 38 Training Objective S.SA1-02-A Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of cause effect relationship between SAS and IAS.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

SF8.079.K1.01 Safety Function 8 Tier 2 Group 2 RO Imp: 3.0 SRO Imp: 3.1 Knowledge of the physical connections and/or cause- effect relationships between the SAS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

IAS Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 66 ID: 2169420 Points: 1.00 Per OP-AA-103-102, WATCH-STANDING PRACTICES, the unit NSO shall perform MCB walkdowns 1 and 2 must be RECORDED.

A. 1. every hour

2. critical parameters B. 1. every hour

2. unexpected alarms C. 1. every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

2. critical parameters D. 1. every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

2. unexpected alarms Answer A Answer Explanation A - Correct: OP-AA-103-102, section 4.4.1 directs hourly walkdowns by the NSO and recording of critical parameters.

B - Plausible: Section 4.5 requires the NSO to announce unexpected alarms but does not require them to be recorded.

C - Plausible: Section 4.4.2 requires US walkdowns every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D - Plausible: Combination of both distractors.

Question Information Topic 2021 NRC Q66 User ID RG10001-N01 System ID 2169420 Status Active Point Value 1.00 Time (min) 1 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

1NRC Exams Only Question Type Bank Difficulty Test ID: 347808 09/15/2021 156 of 229

2021 RO/SRO NRC Exam Test Key Technical Reference and Revision # OP-AA-103-102 Rev. 20 Training Objective T.AM30-05 Previous 2 Byron NRC Exam Use None References Provided None K/A Justification The question meets the K/A, requires examinee knowledge of operator responsibilities during all modes of operation.

SRO-Only Justification N/A Additional Information From Bwd 2020 NRC exam K/A Reference(s)

P2.1.2 Safety Function 8 Tier 3 Group RO Imp: 4.1 SRO Imp: 4.4 Knowledge of operator responsibilities during all modes of plant operation.

(CFR: 41.10 / 45.13)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 67 ID: 2169421 Points: 1.00 Given the following events during a plant start up, which REQUIRE a plant page announcement per OP-AA-104-101, COMMUNICATIONS?

1. Immediately prior to initial CONTROL bank withdrawl

2. At the source range eight-fold increase hold point

3. When criticality has been observed

4. At the 10-3% RTP hold point for critical data A. 1 and 2 B. 1 and 3 C. 2 and 4 D. 3 and 4 Answer B Answer Explanation A - Incorrect: Plausible because eight-fold is a reactivity hold point.

B - Correct: Per OP-AA-104-101 PA announcements are required at mode changes (withdrawal of control banks) and criticality. Reactivity hold points are not required. Per BGP 100-2A1, the definition of mode change from 3 to 2 is interpreted as being the point when the first Control bank is withdrawn.

C - Incorrect: Plausible because eight-fold and 10-3% RTP are reactivity hold points.

D - Incorrect: Plausible because 10-3% RTP is a reactivity hold point.

Question Information Topic 2021 NRC Q67 User ID RG10014-N01 System ID 2169421 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type New Difficulty Technical Reference and Revision # OP-AA-104-101 Rev. 5 Training Objective T.AM69-01-A Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of conditions for making plant wide announcements.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

P2.1.14 Safety Function 8 Tier 3 Group RO Imp: 3.1 SRO Imp: 3.1 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

(CFR: 41.10 / 43.5 / 45.12)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 68 ID: 2211776 Points: 1.00 Unit 1 is at 100% power, normally aligned.

The RO is performing channel checks for the Shiftly and Daily Operating Surveillance.

Currently, the RO is evaluating a multiple channel parameter with a meter scale of 0-200 psig.

What is the MAXIMUM allowed channel deviation (lowest to highest channel) for a generally acceptable channel check?

A. 6 psig B. 12 psig C. 18 psig D. 25 psig Answer choice A is also considered an Answer B A acceptable answer as 3% is considered the acceptable range used in 0BOSR 0.1-0.

Answer Explanation A - Plausible: 6 psig is a 3% deviation and not considered inoperable. However, a misconception that 6 psig is the limit vs. 6% of scale may lead the candidate to choose this distractor. Also, 6 psig would be correct for a 0-100 psig scale.

B - Correct: Per 1BOSR 0.1-1,2,3, section E.8.a, Acceptable Channel Check is typically +/- 3% (unless otherwise stated) from the average of the readings. In other words, 6% deviation from high to low is generally acceptable to satisfy the Channel Check. 6% of a 0-200 psig scale is 12 psig.

C - Plausible: 18 psig is 9%, and a natural progression of the answers. But not the minimum inoperable deviation. 9% would be correct for a 0-150% scale such as delta T channels.

D - Plausible: 25 psig is slightly more than 12%, and a natural progression of the answers. But not the minimum inoperable deviation.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q68 User ID RG20037-N02 System ID 2211776 Status Active Point Value 1.00 Time (min) 1 Cross Reference Number CLOSED Cognitive Level RO-HI Operator Discipline LO-I 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 Technical Reference and Revision # 1BOSR 0.1-1,2,3 rev.75, Shiftly and Daily Operating Surveillance, section E.8 Training Objective 4C.AM-01 Previous Exam Use None References Provided None K/A Justification The question meets the K/A, requires examinee ability to evaluate plant performance and make operational judgments based on instrument interpretation.

SRO-Only Justification N/A Additional Information From 2020 Bwd NRC exam K/A Reference(s)

P2.1.7 Safety Function 8 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)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 69 ID: 2169423 Points: 1.00 Why do 1BEP ES-0.1 and 2BEP ES-0.1, REACTOR TRIP RESPONSE, have DIFFERENT total gallons of boration added for post trip low RCS temperature and shutdown reactivity (control rods not fully inserted)?

A. RCS volume difference due to different SG tube volumes B. RCS mass difference due to different RCS Tave programs C. RCS volume difference due to different Pressurizer level control programs D. RCS volume difference due to different RCS Hot Leg and Cold Leg piping sizes Answer A Answer Explanation A - Correct: The difference in the number of SG tubes between the Unit 1 (B&W) SGs and the Unit 2 (Westinghouse D-5) SGs accounts for the larger RCS volume on Unit 1 and therefore the larger boration requirements on Unit 1.

B - Incorrect: Plausible because the RCS Tave programs are different. However, the different Tave programs are a function of the different SG efficiency and differences in rated thermal power.

C - Incorrect: Plausible because the 0% pressurizer level programs are different. However, the original plant design was a constant mass system with the Westinghouse D-5 SGs. When Unit 1 replaced the SGs with B&W design the pressurizer level control program was altered slightly due to the difference in the SG primary side volume.

D - Incorrect: Plausible because RCS piping diameters are different from Hot Leg to Cold Leg. However, the piping sizes are consistent between both units.

Question Information Topic 2021 NRC Q69 User ID RG20004-N01 System ID 2169423 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.3 Mechanical components and design features of the reactor 10CFR55 Content primary system.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BEP ES-0.1 Rev. 304, 2BEP ES-0.1 Rev. 304 Training Objective T.U1U201-01C Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to explain the variations in procedural actions between units.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

P2.2.4 Safety Function 8 Tier 3 Group RO Imp: 3.6 SRO Imp: 3.6 (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

(CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 70 ID: 2169424 Points: 1.00 Per AD-AA-101, Processing of Procedures and T&RMs, a proposed procedure change that would result in a change to plant configuration 1 contain a change of intent, and an 2 procedure change should be initiated.

A. 1. does

2. interim B. 1. does NOT

2. interim C. 1. does

2. editorial D. 1. does NOT

2. editorial Answer A Answer Explanation A is correct: Per section 4.2.2 ("The revision changes plant configuration") a plant configuration change is a change of intent and requires an interim change as stated in the answer.

B is incorrect: A change to plant confiiguraiton is a change of intent per the procedure. Plausible because distractor is opposite correct answer.

C is incorrect: A change of intent requires an interim change. Plausible because editorial changes are referred to in AD-AA-101.

D is incorrect: A change to plant confiiguraiton is a change of intent per the procedure and requires an interim change. Plausible because distractor is opposite correct answer and because editorial changes are referred to in AD-AA-101.

Question Information Topic 2021 NRC Q70 User ID RG20006-N01 System ID 2169424 Status Active Point Value 1.00 Time (min) 3 Cross Reference Number CLOSED Cognitive Level RO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # AD-AA-101 Rev. 30 Training Objective T.AM03-02 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to evaluate the change to the plant configuration to determine the change of intent, and be knowledgeable about the procedure change process.

SRO-Only Justification N/A Additional Information From Byron 2014 NRC exam K/A Reference(s)

P2.2.6 Safety Function 8 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) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 71 ID: 2169425 Points: 1.00 A nuisance MCR annunciator has been disabled with the field contact isolation switch for several shifts.

Note: This was NOT a procedure directed action.

Per OP-AA-103-102, WATCH-STANDING PRACTICES, the isolation switch will be TRACKED with the 1 and the disabled alarm will be noted in the 2 .

A. 1. Unit NSO Logs

2. appropriate turnover B. 1. Unit NSO Logs

2. Critical Parameter List C. 1. Equipment Status Tag Log

2. appropriate turnover D. 1. Equipment Status Tag Log

2. Critical Parameter List Answer C Answer Explanation A - Incorrect: Plausible because Unit NSO logs are used to document plant changes but are not used as a tracking device for long term configuration changes.

B - Incorrect: Plausible because Unit NSO logs are used to document plant changes but are not used as a tracking device for long term configuration changes. Also plausible because critical parameter lists can be changed to include changing plant conditions. However, OP-AA-103-102 specifically directs the disable alarm to be noted in the turnover.

C - Correct: Per OP-AA-103-102, section 4.5.7.2.B, If the annunciator mode switch will be re-positioned or the alarm disabled for more than one shift, INITIATE an Equipment Status Tracking (EST) tag to TRACK the abnormal condition or annunciator mode switch position. (Note: use of EST is not required if procedure directed.) and section 4.5.7.2.C, Disabled alarms shall be NOTED within the appropriate turnovers.

D - Incorrect: Plausible because critical parameter lists can be changed to include changing plant conditions. However, OP-AA-103-102 specifically directs the disable alarm to be noted in the turnover.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q71 User ID RG20043-N01 System ID 2169425 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # OP-AA-103-102 Rev. 20 Training Objective T.AM30-04 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the process to track inoperable alarms.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

P2.2.43 Safety Function 8 Tier 3 Group RO Imp: 3.0 SRO Imp: 3.3 Knowledge of the process used to track inoperable alarms.

(CFR: 41.10 / 43.5 / 45.13)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 72 ID: 2169426 Points: 1.00 An NSO is changing radiation alarm setpoints on a non-safety related radiation monitor.

After selecting the appropriate rad monitor icon on the RMS Grid screen, which RMS task bar function will the NSO need to open to change the alarm setpoint?

A. Monitor Items B. Channel Items C. Status D. Trend Answer B Answer Explanation A - Incorrect: The Monitor Items page contains configurable variables that are common to all channels within a radiation monitor such as process and sample flow control, filter control, polling status, etc.

Plausible because it also contains configurable data.

B - Correct: Each applicable radiation monitor channel has specific alarm limits assigned. The Channel Items display page is where the alarm limits are changed by selecting the alert/high alarm limit item and manually inputting a new value for the setpoint.

C - Incorrect: The Status page displays all the alarm function status of the specific channel. Plausible because this page indicates when an alert or high alarm setpoint has been exceeded.

D - Incorrect: The Trend page displays current detector rad levels and compares them graphically to the alert and alarm setpoints. Plausible because the alarm setpoints are also digitally displayed on the Trend page.

Question Information Topic 2021 NRC Q72 User ID RG30005-N02 System ID 2169426 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.11 Purpose and operation of radiation monitoring systems, 10CFR55 Content including alarms and survey equipment.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type New Difficulty Technical Reference and Revision # BOP AR/PR-15 Rev. 5 BCP 400-EWASTE GAS, Rev. 1 Training Objective S.AR1-03-D Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to use radiation monitoring system (RMS) to change alarm setpoints.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

P2.3.5 Safety Function 8 Tier 3 Group RO Imp: 2.9 SRO Imp: 2.9 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.11 / 41.12 / 43.4 / 45.9)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 73 ID: 2169427 Points: 1.00 During a routine "at power" containment entry, the Unit 1 NSO is required to post placards in the MCR during the time personnel are in containment.

Per BAP 1450-1, ACCESS TO CONTAINMENT, which of the following MCR locations are the placards to be posted at?

1. 0PM02J near the Containment Purge controls

2. 1PM06J near the Containment Hatch seal alarm

3. 1PM05J near the Reactor controls

4. 1PM02J near the Turbine controls A. 1 and 2 B. 1 and 3 C. 2 and 4 D. 3 and 4 Answer D Answer Explanation A - Incorrect: 0PM02J is plausible because a placard is placed on the 0PM02J during a containment release per BCP 400-TCNMT/ROUTINE. 1PM06J is plausible because the containment hatch seal annunciator will alarm whenever the personnel pass through the containment equipment hatch.

B - Incorrect: 1PM06J is plausible because the containment hatch seal annunciator will alarm whenever the personnel pass through the containment equipment hatch.

C - Incorrect: 1PM06J is plausible because the containment hatch seal annunciator will alarm whenever the personnel pass through the containment equipment hatch.

D - Correct: Per BAP 1450-1, section 4.3.2 the "Do Not Change Power" placards are to placed at the turbine and reactor panels. The purpose is to remind the operator to adhere to the requirement to not change power level by + 2% while personnel are in containment.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q73 User ID RG30013-N01 System ID 2169427 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # BAP 1450-1 Rev. 45 Training Objective T.AM17-01 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of radiological safety procedures pertaining to containment entry.

SRO-Only Justification N/A Additional Information None K/A Reference(s)

P2.3.13 Safety Function 8 Tier 3 Group RO Imp: 3.4 SRO Imp: 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 43.4 / 45.9 / 45.10)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 74 ID: 2169428 Points: 1.00

An event has occurred on Unit 1 causing elevated containment radiation levels.

The crew has entered emergency procedures and is performing mitigation actions in the procedures.

The US assigned the BOP the task of monitoring RMS for "Adverse Containment" conditions.

Which of the following will be monitored?

A. 1PR01J, CNMT PURGE B. 1AR11J, CONTAINMENT FH ICDT C. 1PR11J, CNMT ATMOS D. 1AR20J, CONTAINMENT HI RNG Answer D Answer Explanation A is incorrect, see explanation below.

B is incorrect, see explanation below.

C is incorrect, see explanation below.

D is correct, The Byron emergency procedures have multiple steps that require different parameter criteria depending upon containment status (adverse vs. not adverse). A note at the beginning of 1BEP-0 defines the criteria for adverse containment and is applicable throughout the WOG EP series. The note lists 1AR020/021 rad skids as the rad monitor to determine adverse containment during high rad conditions. The distractors are all plausible because they are other containment radiation monitors used in either emergency plan procedures or abnormal operating procedures.

Question Information Topic 2021 NRC Q74 User ID RG40017-N01 System ID 2169428 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1BEP-0 Rev. 304 Training Objective T.EP00-06 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of EOP terms and definition, specifically the definition of "adverse containment" as determined by the 1AR020 and 21.

SRO-Only Justification N/A Additional Information Bwd 2016 NRC exam K/A Reference(s)

P2.4.17 Safety Function 8 Tier 3 Group RO Imp: 3.9 SRO Imp: 4.3 Knowledge of EOP terms and definitions.

(CFR: 41.10 / 45.13)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 75 ID: 2169429 Points: 1.00 Which of the following Emergency Procedures will direct that BFRs NOT be implemented during the ENTIRE performance of the procedure?

1. 1BCA-0.0, LOSS OF ALL AC POWER

2. 1BCA-0.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED

3. 1BEP ES-1.3, TRANSFER TO COLD LEG RECIRCULATION

4. 1BCA-1.3, SUMP BLOCKAGE CONTROL ROOM GUIDELINE A. 1&3 B. 1&4 C. 2&3 D. 2&4 Answer B Answer Explanation A - Plausible: All of the listed procedures contain the Note: "Byron Status Trees should be monitored for information only. BFRs should NOT be implemented." However, 1BEP ES-1.3 has a qualifier added to the note that BFRs should not be implemented prior to a specific step. In 1BEP ES-1.3, the qualifier is "prior to step 6 (aligning ECCS pumps to the recirc sump).

B - Correct: All of the listed procedures contain the Note: "Byron Status Trees should be monitored for information only. BFRs should NOT be implemented." However, 1BCA-0.1 and 1BEP ES-1.3 have qualifiers added to the note that BFRs should not be implemented prior to a specific step. In 1BCA-0.1, the qualifier is "prior to step 9 (restoring ECCS pumps to standby). In 1BEP ES-1.3, the qualifier is "prior to step 6 (aligning ECCS pumps to the recirc sump).

C - Plausible: All of the listed procedures contain the Note: "Byron Status Trees should be monitored for information only. BFRs should NOT be implemented." However, 1BCA-0.1 and 1BEP ES-1.3 have qualifiers added to the note that BFRs should not be implemented prior to a specific step. In 1BCA-0.1, the qualifier is "prior to step 9 (restoring ECCS pumps to standby). In 1BEP ES-1.3, the qualifier is "prior to step 6 (aligning ECCS pumps to the recirc sump).

D - Plausible: All of the listed procedures contain the Note: "Byron Status Trees should be monitored for information only. BFRs should NOT be implemented." However, 1BCA-0.1 has a qualifier added to the note that BFRs should not be implemented prior to a specific step. In 1BCA-0.1, the qualifier is "prior to step 9 (restoring ECCS pumps to standby).

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q75 User ID RG40020-N01 System ID 2169429 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level RO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # 1BCA-0.0 Rev. 304, 1BCA-0.1 Rev. 301, 1BCA-1.3 Rev. 302, 1BEP ES-1.3 Rev. 304 Training Objective T.AM04-17 Previous 2 Byron NRC Exam Use None References Provided None K/A Justification Question meets KA - question requires examinee knowledge of operational implications of EOP notes.

SRO-Only Justification N/A Additional Information From Bwd 2020 NRC exam K/A Reference(s)

P2.4.20 Safety Function 8 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)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 76 ID: 2169430 Points: 1.00

An RCS LOCA occurred on loop 1A.

1BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, is in progress at step 12, CHECK IF RCS COOLDOWN AND DEPRESSURIZATION IS REQUIRED.

Simultaneously, status tree monitoring identified a YELLOW path for Integrity due to 1A cold leg temperature and excessive cool down rate.

RCS pressure is currently 1200 psig and stable at step 12.

What procedural guidance will the SRO follow next?

A. Continue in 1BEP-1 to step 13.

B. Go to 1BEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION.

C. Go to 1BFR-P.1 RESPONSE TO IMMINENT PRESSURIZER THERMAL SHOCK CONDITION.

D. Go to 1BFR-P.2 RESPONSE TO ANTICIPATED PRESSURIZER THERMAL SHOCK CONDITION.

Answer B Answer Explanation A - Plausible: Remain in BEP-1 would be correct if RCS pressure was less than 325 psig and RH was in service.

B - Correct: Per 1BEP-1, with RCS pressure greater than 325 psig, transition is made to 1BEP ES-1.2.

C - Plausible: 1BFR-P.1 would be correct if the status tree was in an orange or red condition.

D - Plausible: 1BFR-P.2 would be correct if the unit was not already in the emergency procedures.

Yellow path status tree procedures are used only as time permits and do not take precedence over other in progress emergency procedures. Per BAP 1310-10, The EOP and its Operator Action Summary Page has priority over the yellow path function restoration guidelines.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q76 User ID SE10009-N03 System ID 2169430 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BEP-1 Rev. 302 Training Objective T.EP02-01-B Last 2 Byron NRC Previous Exam Use None References Provided None K/A Justification The question meets the K/A, requires examinee ability to determine the actions to be taken (procedure flow path) if PTS limits are violated during a small break LOCA.

SRO-Only Justification The question is SRO ONLY because it requires assessing of plant conditions and selection of procedure to mitigate the conditions.

Additional Information None K/A Reference(s)

EPE.009.EA2.14 Safety Function 3 Tier 1 Group 1 RO Imp: 3.8 SRO Imp: 4.4 Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 / 45.13)

Actions to be taken if PTS limits are violated Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 77 ID: 2212721 Points: 1.00

Unit 1 is at 20% power, ramping down at 5 MW/min per 1BGP 100-4, POWER DESCENSION.

The 1A RCP had elevated but stable lower bearing temperature.

One minute ago the 1A RCP lower bearing temperature began rising again.

1-7-C2 RCP LOWER BRNG TEMP HIGH annunciator has alarmed.

The crew has entered 1BOA RCP-2 LOSS OF SEAL COOLING UNIT 1.

1. Per 1BOA RCP-2 Step 2, MONITOR RCP TEMPERATURES, what is the lower bearing temperature at which 1A RCP must be tripped?

2. If the maximum lower bearing temperature is exceeded, what will the SRO direct?

A. 1. 195°F

2. Trip the RCP and shutdown the reactor per 1BGP 100-5, PLANT SHUTDOWN AND COOLDOWN while continuing with 1BOA RCP-2.

B. 1. 225°F

2. Trip the RCP and shutdown the reactor per 1BGP 100-5, PLANT SHUTDOWN AND COOLDOWN while continuing with 1BOA RCP-2.

C. 1. 195°F

2. Trip the Reactor, trip 1A RCP , and then enter 1BEP-0, REACTOR TRIP OR SAFETY INJECTION while continuing with 1BOA RCP-2.

D. 1. 225°F

2. Trip the Reactor, trip 1A RCP , and then enter 1BEP-0, REACTOR TRIP OR SAFETY INJECTION while continuing with 1BOA RCP-2.

Answer D Answer Explanation A - Incorrect: 195°F is plausible because it is the maximum motor bearing temperature that an RCP is allowed to operate at per BOP RC-1. 1BGP-100-5 is plausible because the reactor will not automatically trip on a single RCP trip with power below P-8. However, the plant safety analysis does not consider 3 loop operation in Mode 1. Additionally, Tech Spec 3.4.4 does not allow 3 loop operation. Therefore, continuing the shutdown into Mode 2 and using 1BGP 100-5 violates the plant safety analysis and TS 3.4.4 and is incorrect. Per BAR 1-13-A3, IF in MODE 1 or 2, and RCP breaker has opened or low flow conditions (<90%) exist, THEN VERIFY/INITIATE reactor trip and go to 1BEP-0, Reactor Trip or Safety Injection Unit 1.

B - Incorrect: 225°F is plausible because Per 1BOA RCP-2, an RCP must be tripped if lower bearing temperature exceeds 225°F.. See answer A explanation for 2nd part plausibility.

C - Incorrect: 195°F is plausible because it is the maximum motor bearing temperature that an RCP is allowed to operate at per BOP RC-1.

D - Correct: Per 1BOA RCP-2, an RCP must be tripped if lower bearing temperature exceeds 225°F.

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2021 RO/SRO NRC Exam Test Key The RNO of 1BOA RCP-2 Step 2.a RNO directs trip the reactor, trip the affected RCP, perform 1BEP-0 while continuing with this procedure.

Question Information Topic 2021 NRC Q77 User ID SE10017-N01 System ID 2212721 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BOA RCP-2 Rev 111, BOP RC-1 Rev. 48, BAR 1-13-A3 Rev. 4 Training Objective T.EP01-06-A Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to determine when to trip an RCP on high bearing temperature.

SRO-Only Justification The question is SRO ONLY because it requires assessing of plant conditions and selection of procedure to mitigate the conditions.

Additional Information None K/A Reference(s)

APE.015/017.AA2.08 Safety Function 4 Tier 1 Group 1 RO Imp: 3.4 SRO Imp: 3.5 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): (CFR: 43.5 / 45.13)

When to secure RCPs on high bearing temperature Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 78 ID: 2169432 Points: 1.00

Unit 1 is at 100% power.

An event occurs and the following annunciators alarm.

1-9-A3 CHG PUMP TRIP

1-9-D3 CHG LINE FLOW HIGH LOW

1-9-A1 REGEN HX LTDWN TEMP HIGH What will be the FIRST action the SRO will direct?

A. Isolate Letdown B. Start the standby CV Pump C. Vent the standby CV Pump D. Place 1CV129, DEMIN HI TEMP LTDWN DIVERT VLV, to the HUT position Answer A Answer Explanation A - Correct: All three alarms indicate a loss of charging flow. With no cooling to the Regen Heat Exchanger, the priority is to isolate letdown. BHC 1-9-A3 directs letdown to be isolated first, then respond to the pump trip per the BAR. BAR 1-9-A3 also directs letdown to be isolated first prior to responding to the tripped CV pump. BAR 1-9-A1 first action is to match charging and letdown flow, however with charging not available to restore regen heat exchanger temperature, it then directs isolating letdown.

B - Incorrect: Plausible because BAR 1-9-A3 directs the alternate CV pump to be started AFTER letdown is isolated.

C - Incorrect: Plausible because if gas binding of the tripped CV pump is suspected (due to pre-trip indications) BAR 1-9-A9 directs entry into 1BOA PRI-15. 1BOA PRI-15 will verify gas binding of the previously running CV pump and then vent the standby CV pump prior to starting it.

D - Incorrect: Plausible because a similar letdown high temperature alarm, 1-9-E2, LTDWN TEMP HIGH list an auto action of 1CV129 diverting to the VCT position (bypassing the demineralizers. A plausible operator action is to manually backup automatic actions. However, the question stem does not list annunciator 1-9-E2 because cooling is still available to the Letdown Heat Exchanger.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q78 User ID SE10022-N01 System ID 2169432 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # BHC 1-9-A3 Rev. 0 Training Objective T.OA23A-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to prioritize alarms during a loss of reactor coolant makeup event.

SRO-Only Justification The question is SRO only because it requires knowledge of detailed procedure steps and step sequences within several procedures.

Additional Information None 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)

GE.4.0.APE.022 Safety Function 2 Tier 1 Group 1 RO Imp: SRO Imp:

Loss of Reactor Coolant Makeup Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 79 ID: 2169433 Points: 1.00 A SGTR has occurred on Unit 1, and the crew is performing 1BEP-3, STEAM GENERATOR TUBE RUPTURE.

The ruptured S/G has been isolated.

The RCS has been cooled down and depressurized.

ECCS flow has been terminated.

ALL RCPs are stopped.

RVLIS head level is 100%.

RCS pressure is 1050 psig.

CETCs are 500 °F.

PZR level is 61%.

When RCP support conditions are established, what will the US direct regarding RCP starts?

A. NOT start an RCP because the rate of SG tube leakage will rise.

B. NOT start an RCP to prevent pressurized thermal shock.

C. Start one RCP to minimize localized boron dilution.

D. Start one RCP because natural circulation will NOT allow cooldown of the ruptured SG.

Answer C Answer Explanation A - Plausible: NOT start an RCP because the rate of S/G tube leakage will rise is incorrect. Starting an RCP will result in a pressure transient in the RCS. An examinee could reasonably infer that this transient would lead to increased SG tube leakage.

B - Plausible: NOT start an RCP because pressurized thermal shock concerns will rise is incorrect.

Starting an RCP will result in a pressure transient in the RCS. An examinee could reasonably infer that this transient would lead to increased risk of pressurized thermal shock.

C - Correct: Start one RCP because pressurized thermal shock concerns will lower is correct. From the background document, it is desirable to start an RCP "to provide normal pressurizer spray and to ensure homogeneous fluid temperatures and boron concentrations. In addition to minimizing pressurized thermal shock and boron dilution concerns, this also aids in cooling the ruptured SG."

D - Plausible: Start one RCP because natural circulation will NOT allow cooldown of the ruptured SG.

This is plausible since the ruptured SG will be isolated and the examinee may have a conceptual Test ID: 347808 09/15/2021 182 of 229

2021 RO/SRO NRC Exam Test Key misunderstanding leading them to infer that the SG won't cooldown.

Question Information Topic 2021 NRC Q79 User ID SS20002-G2.4.18-91 System ID 2169433 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # BD-EP-3 Rev. 300, 1BEP-3 Rev. 303 Training Objective T.EP04-08 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to interpret and execute procedure steps.

SRO-Only Justification SRO level because examinee must assess the plant conditions and have knowledge of the diagnostic steps and decision points in the EOPs.

The SRO would be deciding if the RCP was going to be started. The SRO also must have specific knowledge of the content of the procedure versus just the procedures overall mitigative strategy.

Additional Information From 2019 Bwd NRC exam.

K/A Reference(s)

P2.1.20 Safety Function 2 Tier 3 Group RO Imp: 4.6 SRO Imp: 4.6 Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12)

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

Steam Generator Tube Rupture (SGTR)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Test ID: 347808 09/15/2021 183 of 229

2021 RO/SRO NRC Exam Test Key Cross Reference Links None Test ID: 347808 09/15/2021 184 of 229

2021 RO/SRO NRC Exam Test Key Question 80 ID: 2169434 Points: 1.00

Unit 1 was at 100% power.

The following occurs:

DC bus 113 faults and is de-energized.

The crew manually trips the reactor.

The crew is performing 1BEP ES-0.1, REACTOR TRIP RESPONSE, and 1BOA ELEC-1, LOSS OF DC BUS, concurrently.

30 seconds later, an EO locally trips the Q10 and Q20 exciter breakers.

All equipment operates as expected.

1. With NO additional operator actions, one minute AFTER the reactor trip, which MCR indications will be UNAVAILABLE?

2. When the crew re-energizes Bus 143 per 1BOA ELEC-1, what procedure will the SRO specify for local operation of Bus 143 breakers?

A. 1. ALL Annunciators

2. 1BOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT B. 1. ALL Annunciators

2. 1BOA PRI-5, CONTROL ROOM INACCESSIBILITY C. 1. The SER display

2. 1BOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT D. 1. The SER display

2. 1BOA PRI-5, CONTROL ROOM INACCESSIBILITY Answer A Answer Explanation A is correct, On a loss of Non-ESF DC 113 bus, and a reactor trip, power will be loss to AC busses 143 and 157 also. Bus 143 (via MCC 133V2) and DC bus 113 are the normal and reserve power supplies to the 1PA19J, Annunciator Logic Cabinet. With both power supplies lost, NO annunciators will be available as they are processed thru the logic cabinet. Per 1BOA ELEC-1, Bus 143 breakers are operated per 1BOA ELEC-5. Specifically, ATTACHMENT A, 4KV or 6.9KV Breaker Local Operation.

B is incorrect, plausible because 1BOA PRI-5, ATTACHMENT B, Local Operator Actions, contains local operation of 4KV equipment. 1BOA PRI-5 is referenced in several EP and OA procedures for use to actuate equipment if normnal operations do not work. Specific examples are found in BEP-1 Steps 4, 7e, 8, and 14d RNO and BOA PRI-10 has a note at the beginning of the procedure to allow use of PRI-5 to support any local operations.

C is incorrect, Plausible because, if the DC bus lost had been DC bus 114, the result would have been loss of complete power to the 1PA42J which would result in losing the SER display.

D is incorrect, see explanation for response B and C.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q80 User ID SE10058-N03 System ID 2169434 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BOA ELEC-1 Rev. 105 Training Objective T.OA01-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge that a loss of a DC bus will have on the ability to monitor plant systems and impact on operating equipment.

SRO-Only Justification The question is SRO ONLY because it requires assessing of plant conditions and selection of procedure to mitigate the conditions.

Additional Information None K/A Reference(s)

APE.058.AA2.03 Safety Function 6 Tier 1 Group 1 RO Imp: 3.5 SRO Imp: 3.9 Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 / 45.13)

DC loads lost; impact on ability to operate and monitor plant systems Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 186 of 229

2021 RO/SRO NRC Exam Test Key Question 81 ID: 2169435 Points: 1.00 Unit 2 was at 100% power.

The crew manually tripped Unit 2 and initiated SI in response to an RCS LOCA.

The crew transitioned from 2BEP-0, REACTOR TRIP AND SI, to 2BCA-1.2, LOCA OUTSIDE CONTAINMENT.

The leak has been isolated by closing 2SI8809B, RH TO COLD LEGS 2B + 2C ISOL VLV.

RCS pressure is RISING.

What is the next procedure the SRO will direct transition to?

A. 2BEP-0, REACTOR TRIP OR SI B. 2BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT C. 2BCA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION D. 2BEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION Answer B Answer Explanation A - Plausible because several emergency procedure transitions have completion transitions by "Returning to procedure previously in progress and step in affect".

B - Correct: 2BCA-1.2 directs transition to 2BEP-1 if the leak is isolated and RCS pressure is rising.

C - Plausible because 2BCA-1.2 directs transition to 2BCA-1.1 if RCS pressure is NOT rising, i.e. the attempts to isolate the leak was not successful.

D - Plausible because 2BEP-1 will direct transition to 2BEP ES-1.2 if an active RCS LOCA was determined.

Question Information Topic 2021 NRC Q81 User ID SE1WE04-N02 System ID 2169435 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I CFR: 43.5 Assessment of facility conditions and selection of appropriate 10CFR55 Content procedures during normal, abnormal, and emergency situations.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 2BCA-1.2 Rev.300 Training Objective S-CA-014 Byron 2 Previous NRC Exam Use None References Provided None K/A Justification This question meets the K/A, because the examinee must evaluate plant performance and make operational judgements based on operating characteristics.

SRO-Only Justification This question is SRO level because the examinee must determine appropriate procedure transition.

Additional Information None K/A Reference(s)

P2.1.7 Safety Function 6 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.4.5.E04 Safety Function 3 Tier 1 Group 1 RO Imp: SRO Imp:

LOCA Outside Containment Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 188 of 229

2021 RO/SRO NRC Exam Test Key Question 82 ID: 2169436 Points: 1.00

Unit 1 was at 100% power.

Subsequently, one control rod dropped to the bottom of the core.

The crew entered 1BOA ROD-3, DROPPED OR MISALIGNED ROD, and Tech Spec 3.1.4, Rod Group Alignment Limits.

The rod is ready to be recovered at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the drop.

The QNE and crew agree the rod recovery will take 30 minutes.

PDMS is INOPERABLE.

1. With the above conditions, what does 1BOA ROD-3 specify as the proper reactor power for the rod recovery?

2. With the above conditions, what, if any, is the maximum power requirement of TS 3.1.4?

1BOA ROD-3 TS 3.1.4 A. <50% limit of 75%

B. <50% No specified limit C. <70% limit of 75%

D. <70% No specified limit Answer C Answer Explanation A - Incorrect: Plausible because 1BOA ROD-3 specifies a <50% reactor power limit if the rod is not recovered within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B - Incorrect: Plausible because 1BOA ROD-3 specifies a <50% reactor power limit if the rod is not recovered within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Also, when PDMS is OPERABLE, LHR is measured continuously. Therefore, a reduction of power to 75% RTP is not necessary to ensure that local LHR increases due to a misaligned RCCA will not cause the core design criteria to be exceeded.

C - Correct: Per 1BOA ROD-3, step 10, if rod recovery is within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the drop, the limit is <70%

reactor power. Additionally, TS 3.1.4 bases specifies a <75% reactor power limit if PDMS is INOPERABLE.

D - Incorrect: Plausible because if PDMS is operable, there is no specific reactor power limit during power operation, Test ID: 347808 09/15/2021 189 of 229

2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q82 User ID SE10003-N02 System ID 2169436 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # B 3.1.4 Rev.59, 1BOA ROD-3 Rev.114 Training Objective T.OA34-10 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of conditions and limitations in facility license (TS 3.1.4 bases).

SRO-Only Justification The question is SRO ONLY because it requires knowledge of Tech Spec bases.

Additional Information None K/A Reference(s)

P2.2.38 Safety Function 3 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)

GE.4.0.APE.003 Safety Function 1 Tier 1 Group 2 RO Imp: SRO Imp:

Dropped Control Rod Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 190 of 229

2021 RO/SRO NRC Exam Test Key Question 83 ID: 2169437 Points: 1.00

Unit 1 is at 50% power.

The 1A CW Pump is OOS.

Subsequently the following occurs:

The 1C CW pump TRIPS on overcurrent.

1CW001C, 1C PP DSCH VLV, is stuck OPEN and its breaker trips.

Condenser pressure begins slowly rising.

The crew enters 1BOA SEC-3, LOSS OF CONDENSER VACUUM.

What is the first action the SRO will direct in 1BOA SEC-3?

A. TRIP the reactor and enter 1BEP-0 REACTOR TRIP OR SI.

B. TRIP the turbine and enter 1BOA TG-8 TURBINE TRIP BELOW P8.

C. RAMP the turbine down per 1BGP 100-4 POWER DESCENSION.

D. START the U-1 Hogging Vacuum Pump per BOP OG-1, HOGGING VACUUM PUMP STARTUP.

Answer A Answer Explanation A - Correct: Per 1BOA SEC-3, step 1, IF ANY discharge valve on a non-running pump will not close and there are <2 CW pumps running, THEN manually trip the reactor. GO TO 1BEP-0, REACTOR TRIP OR SAFETY INJECTION.

B - Incorrect: Plausible because the reason to shut down the unit is the affect on the turbine during a loss of condenser vacuum. Several other BOA procedures direct a turbine trip when power is below P8, however at 50% power, tripping the turbine would not be correct.

C - Incorrect: Plausible because several other procedures direct ramping the turbine down during secondary transients.

D - Incorrect: Plausible because 1BOA SEC-3, step 4, directs starting the U-1 Hogging Vacuum Pump to restore condenser vacuum. However, with the given stem conditions, the crew would have transitioned to 1BEP-0 before reaching step 4.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q83 User ID SE10051-N01 System ID 2169437 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BOA SEC-3 Rev. 107 Training Objective T.OA38-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to interpret conditions for a reactor trip during a loss of condenser vacuum event.

SRO-Only Justification The question is SRO ONLY because it requires detailed procedure knowledge that is not contained within a note, caution or OAS.

Additional Information None K/A Reference(s)

APE.051.AA2.02 Safety Function 4 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 Condenser Vacuum: (CFR: 43.5 / 45.13)

Conditions requiring reactor and/or turbine trip Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 192 of 229

2021 RO/SRO NRC Exam Test Key Question 84 ID: 2211801 Points: 1.00

A reactor trip and Safety Injection have occurred on Unit 1.

The crew was performing actions of 1BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Due to conflicting indications, the crew entered 1BEP ES-0.0, REDIAGNOSIS.

While performing 1BEP ES-0.0, the crew determines that there is a rising trend on secondary plant radiation monitors AND one S/G level is rising faster than the other three with Auxiliary Feedwater flow being equal to all S/Gs.

Which one of the following describes how the US will transition from 1BEP ES-0.0, REDIAGNOSIS to the correct procedure?

A. Go directly to 1BEP-3, STEAM GENERATOR TUBE RUPTURE, or 1BCA-3 series procedure.

B. Return to 1BEP-0, REACTOR TRIP OR SI, diagnostic steps to verify indications, then transition to 1BEP-3, STEAM GENERATOR TUBE RUPTURE.

C. Use Heat Sink status tree for transition to 1BFR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL.

D. Return to 1BEP-1 step in effect and use the Operator Action Summary page for transition to 1BEP-3, STEAM GENERATOR TUBE RUPTURE.

Answer A Answer Explanation A - Correct: 1BEP ES-0.0, step 4 directs transition to 1BEP-3 or 1BCA-3 series procedures.

B - Incorrect: Plausible: Several emergency procedures transition back to 1BEP-0 when previously undiagnosed conditions require safety injection to mitigate the condition. However, there is no transition back to 1BEP-0 from 1BEP ES-0.0.

C - Incorrect: Plausible: 1BFR-H.3 addresses Steam Generator high level and procedure transitions have occurred which requires monitoring the BFR procedure entries. 1BFR-H.3 is a yellow condition entry and, per BAP 1310-10 HU-AA-104-101, PROCEDURE USE AND ADHERENCE, BYRON ADDENDUM does not take precedence over an EP procedure which would address the causulty. While the yellow path BFR is performed based on operator judgement, choosing to address the yellow path prior to addressing the EP is incorrect based on the higher priorty procedure needing to be implemented.

D - Incorrect: Plausible: Transition back to 1BEP-1 from 1BEP ES-0.0 is required if NO indication of a SG tube rupture is noted.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q84 User ID SE1WE01-N01 System ID 2211801 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 1BEP ES-0.0 Rev. 300, BAP 1310-10 Rev 21 Training Objective 7D.EP-001-B Previous 2 Byron NRC Exams Use Similar to Byr NRC 19-1 question 25 References Provided None K/A Justification The question meets the K/A, requires knowledge of EOP entry conditions.

SRO-Only Justification The question is SRO level because it requires assessment of plant conditions and selection of the proper procedure flowpath.

Additional Information From Bwd 2020 NRC exam K/A Reference(s)

P2.4.1 Safety Function 4 Tier 3 Group RO Imp: 4.6 SRO Imp: 4.8 Knowledge of EOP entry conditions and immediate action steps.

(CFR: 41.10 / 43.5 / 45.13)

GE.4.5.E01 Safety Function 3 Tier 1 Group 2 RO Imp: SRO Imp:

Rediagnosis Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 194 of 229

2021 RO/SRO NRC Exam Test Key Question 85 ID: 2169438 Points: 1.00

Unit 1 is at 100% power.

Letdown flow is currently 75 gpm.

The other two (2) letdown orifice isolation valves are CLOSED, but available.

All other equipment is normally aligned for this power level.

Elevated RCS coolant activity is reported by Chemistry and the crew enters 1BOA PRI-4, HIGH REACTOR COOLANT ACTIVITY and Tech Spec 3.4.16, RCS SPECIFIC ACTIVITY.

1. What is the mitigation strategy of 1BOA PRI-4?

2. Per the bases for LCO 3.4.16, RCS Specific Activity, RCS specific activity limits prevent exceeding dose acceptance criteria for which event(s)?

A. 1. MAXIMIZE letdown

2. SGTR or MSLB B. 1. MAXIMIZE letdown

2. RCS LOCA outside containment C. 1. ISOLATE letdown

2. SGTR or MSLB D. 1. ISOLATE letdown

2. RCS LOCA outside containment Answer A Answer Explanation A is correct, The mitigation strategy of 1BOA PRI-4 includes maximizing letdown to clean up the RCS with a mixed bed demin. The bases for Tech Spec 3.4.16 specifically list the accidents of SGTR and MSLB as events the LCO limits are intended to prevent exceeding dose limits during.

B is incorrect, Plausible because elevated RCS activity would raise dose rates outside containment during a LOCA outside containment.

C is incorrect, Plausible because isolating letdown would reduce dose rates in the aux bldg.

D is incorrect, see plausibility statement of distractors B and C.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q85 User ID SE20076-N01 System ID 2169438 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I 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 Technical Reference and Revision # 1BOA PRI-4 Rev.103, B 3.4.16 Rev. 72 Training Objective T.OA15-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to determine corrective actions associated with high RCS activity.

SRO-Only Justification The question is SRO ONLY because it requires knowledge of Tech Spec bases.

Additional Information From 2011 Bwd NRC exam K/A Reference(s)

APE.076.AA2.02 Safety Function 9 Tier 1 Group 2 RO Imp: 2.8 SRO Imp: 3.4 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity: (CFR: 43.5 /

45.13)

Corrective actions required for high fission product activity in RCS Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 196 of 229

2021 RO/SRO NRC Exam Test Key Question 86 ID: 2169439 Points: 1.00

Unit 1 is in Mode 4 plant with a plant cooldown in progress.

RCS is 220°F and 200 psig.

1A RH train is in Shutdown Cooling per BOP RH-6, OPERATION OF THE RH SYSTEM IN SHUTDOWN COOLING.

1RH8716A, HX 1A DSCH XTIE VLV, is CLOSED and energized.

1B RH train is aligned for ECCS injection.

An electrical short causes 1RH8716A power supply breaker to TRIP.

With the above conditions, what is the 1B RH train operability status and why/what action should be taken?

A. OPERABLE because 1RH8716B is OPEN.

B. OPERABLE because 1RH8716A can be LOCALLY opened.

C. INOPERABLE and 1RH8716A should be LOCALLY opened in the current plant configuration to return status to operable.

D. INOPERABLE and the plant cooldown should CONTINUE to MODE 5 in the current plant configuration to get out of an applicable Mode.

Answer D Answer Explanation A - Incorrect: Both RH discharge cross tie valves need to be open to allow a single train to inject into all four RCS cold legs. In the current plant configuration, the 1RH8716A must be able to be opened from the MCR to maintain 1B RH train operable per BOP RH-6. Plausible because 1RH8716A can be locally opened.

B - Incorrect: 1RH8716A must be able to be opened from the MCR to maintain 1B RH train operable per BOP RH-6 and TS 3.5.3 bases. Plausible because 1RH8716A can be locally opened.

C - Incorrect: Opening 1RH8716A in the current plant configuration would lift the 1B RH train suction relief. Plausible because 1RH8716A can be locally opened.

D - Correct: TS 3.5.3, condition A requires immediate action to restore ECCS subsystem. Because the single valve failure would render either RH train inoperable, the quickest way to exit the LCO is to continue the cooldown to mode 5. Applying LCO 3.0.2, If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated. The only other action that would satisfy the LCO action would be to secure the 1A RH train from shutdown cooling and then open 1RH8716A locally. However, this was not given in the possible answer choices.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q86 User ID SS20005-N02 System ID 2169439 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # TS 3.5.3 Amendment 182, BOP RH-6 Rev. 52 Training Objective S.RH1-13 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict the impact of malfunction in RH system on low temperature overpressure (LTOP) protection. (1RH8716A is closed to prevent lifting of 1B RH suction relief from the 1A RH pump discharge pressure, while the 1B RH suction relief is aligned for ECCS and can be credited for LTOP.

Also, requires the SRO to use procedures to mitigate the conditions. In this case, continuing the plant cooldown per 1BGP 100-5.

SRO-Only Justification The question is SRO ONLY because it requires assessment of plant conditions and determining operability and applying tech spec by selecting action to place the unit outside a mode of applicability.

Additional Information None K/A Reference(s)

SF4.005.A2.02 Safety Function 4 Tier 2 Group 1 RO Imp: 3.5 SRO Imp: 3.7 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)

Pressure transient protection during cold shutdown Test ID: 347808 09/15/2021 198 of 229

2021 RO/SRO NRC Exam Test Key Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 199 of 229

2021 RO/SRO NRC Exam Test Key Question 87 ID: 2169440 Points: 1.00 The U-1 reactor automatically tripped from full power after the 1A FRV failed closed.

What is the MAXIMUM allowable time to complete the ENS notification?

[REFERENCE PROVIDED]

A. 30 minutes B. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Answer C Answer Explanation A - Incorrect: Plausible because, if the event required a EAL declaration, the maximum time limit would be 15 minutes to classify and then 15 minutes to report it to state and local governments (from the time of declaration) for a possible total of 30 minutes.

B - Incorrect: Plausible because 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months would be correct if an EAL condition existed. The maximum time limit to report an EAL classification to the NRC is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C - Correct: Per SAF 1.6, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is maximum time limit to report an RPS actuation when the reactor is critical to the NRC.

D - Incorrect: - Plausible because 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is maximum time limit to report an RPS actuation (inadvertent) when the reactor is not critical.

Question Information Topic 2021 NRC Q87 User ID BWLC7EAM2013 System ID 2169440 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number OPEN Cognitive Level SRO-HIGH Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

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2021 RO/SRO NRC Exam Test Key NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # LS-AA-1110 Rev. 31 Training Objective T.AM43-05 Previous 2 Byron NRC Exams Use None References Provided Mid-West Reportability Manual K/A Justification Question meets the K/A, requires examinee knowledge of events (RPS actuation) that must be reported to external agencies.

SRO-Only Justification The question is SRO ONLY because assessing reportability is an SRO function. Per EP-AA-112-100-F-01, Shift Emergency Director Checklist, the Shift Emergency Director has responsibility for ENS reportability. This is the SM or SRO designee in the MCR.

Additional Information From Bwd LOR bank.

K/A Reference(s)

GS.3.0.SF7.012 Safety Function 7 Tier 2 Group 1 RO Imp: SRO Imp:

Reactor Protection System P2.4.30 Safety Function 7 Tier 3 Group RO Imp: 2.7 SRO Imp: 4.1 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

(CFR: 41.10 / 43.5 / 45.11)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 201 of 229

2021 RO/SRO NRC Exam Test Key Question 88 ID: 2169441 Points: 1.00

Unit 1 experienced an RCS LOCA inside containment.

Containment pressure peaked at 22 psig.

Containment pressure is 18 psig and SLOWLY LOWERING.

All four RCFCs are running in slow speed.

1BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, is in progress.

The crew has just completed initial performance of step 7, CHECK IF CS SHOULD BE STOPPED.

Per 1BEP-1, when will the CS pumps be secured?

(step 7.b table provided below for reference)

Step 7.b. Determine number of CS pumps required from table:

CONTAINMENT RCFCs CS PUMPS PRESSURE RUNNING IN REQUIRED ACCIDENT MODE GREATER THAN --- 2 50 PSIG BETWEEN --- 2 15 PSIG and 50 PSIG AND RISING BETWEEN 0 or 1 2 15 PSIG and 50 2, 3, or 4 1 PSIG AND DROPPING LESS THAN 15 --- 0 PSIG A. BOTH pumps will be secured in step 7.

B. ONE pump will be secured in step 7, and the remaining pump will be secured after it has operated for at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

C. ONE pump will be secured in step 7, and the remaining pump will be secured as soon as containment pressure drops to <15 psig.

D. NEITHER pump will be secured in step 7, however BOTH will be secured as soon as containment pressure drops to <15 psig.

Answer B Answer Explanation A - Incorrect: Plausible because this would be correct if containment pressure was <15 psig during step 7 initial performance.

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2021 RO/SRO NRC Exam Test Key B - Correct: 1BEP-1, step 7 table, only 1 CS pump is required with containment pressure between 15 and 50 psig AND 2 or more RCFCs running in accident mode. Therefore, one CS pump will be stopped during step 7. 1BEP-1 CAS requires at least one CS pump to continue operation for at least 8 hrs if the actuation was due to a primary LOCA.

C - Incorrect: Plausible because step 7 RNO and CAS directs the second pump to be secured as soon as containment pressure drops <15 psig. (for secondary breaks CS can be shutdown when containment pressure drops below 15 psig).

D - Incorrect: Plausible if <2 RFCS were operating in emergency mode.

Question Information Topic 2021 NRC Q88 User ID SS20026-N01 System ID 2169441 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 1BEP-1 Rev. 302 Training Objective T.EP02-01-D Previous Exam Use None References Provided 1BEP-1 step 7.b (in question stem)

K/A Justification Question meets the K/A, requires examinee knowledge of when it is safe to secure CS pumps.

SRO-Only Justification Question is SRO ONLY because it requires detailed procedure knowledge not included in the notes, cautions, OAS or CAS. (1BEP-1 step 7)

Additional Information From Bwd LORT K/A Reference(s)

SF5.026.A2.08 Safety Function 5 Tier 2 Group 1 RO Imp: 3.2 SRO Imp: 3.7 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; 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)

Safe securing of containment spray when it can be done)

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2021 RO/SRO NRC Exam Test Key Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 204 of 229

2021 RO/SRO NRC Exam Test Key Question 89 ID: 2169442 Points: 1.00

Unit 1 has experienced a steam generator tube rupture on the 1A SG.

The crew is performing 1BEP-3, STEAM GENERATOR TUBE RUPTURE, step 4.b, CLOSE RUPTURED SG AF ISOL VALVES AND THROTTLE VALVES.

When isolating AF flow to the 1A SG the following occurred:

1AF013A, S/G 1A ISOL VLV, fully CLOSED.

1AF013E, S/G 1A ISOL VLV, FAILED to close.

1AF005A, S/G 1A FLOW CONT VLV, Controller was adjusted to 0% demand.

1AF005E, S/G 1A FLOW CONT VLV, Controller was adjusted to 0% demand.

1. Is 1A SG AF isolation adequate per 1BEP-3?

2. What additional actions, if any, need to be taken?

A. 1. Yes

2. NO additional actions are required.

B. 1. NO

2. 1AF005E must be locally isolated with the handwheel.

C. 1. NO

2. 1AF013E must be locally isolated with the handwheel.

D. 1. NO

2. The 1B AF Pump must be shutdown.

Answer B Answer Explanation A - Incorrect: Plausible because the 1AF005 valve will go to fully closed position indication when the controller is set to 0%.

B - Correct: Per 1BEP-3, step 4.b A/ER column, the 1AF013 valves and the 1AF005 valves are closed from the MCR on the ruptured SG. If a 1AF013 valve fails to close, the RNO action is to locally close the associated 1AF005 valves with the handwheel. The 1AF005 flow control valves can experience significant leakby with the MCR controllers set to 0%. Therefore, a WOG 3 revision requirement to 1BEP-3 requires the local action.

C - Incorrect: Plausible because the 1AF013 valve do have handwheels to locally close the valves and the 1AF013 valve was the failed valve. However, the 1AF013 valves are located in the AF tunnels which have flood seals over the access hatches. Accessing the 1AF013 valves would be a untimely action because maintenance is required to remove the flood seals.

D - Incorrect: Plausible because only 1 AF pump is required for the intact SGs to maintain a heat sink per TS 3.7.5 bases. Shutting down the 1B AF pump would secure flow to the 1A SG, however, 1BEP-3 does not direct this action.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q89 User ID SS20061-N01 System ID 2169442 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 New Difficulty Technical Reference and Revision # 1BEP-3 Rev. 303 Training Objective T.EP04-08 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee to predict the impact of an MOV failure on the AF system and use procedures to mitigate the failure.

SRO-Only Justification The question is SRO ONLY because it requires detailed procedure knowledge that is not contained in notes, cautions, OAS or CAS.

Additional Information None K/A Reference(s)

SF4.061.A2.07 Safety Function 4 Tier 2 Group 1 RO Imp: 3.4 SRO Imp: 3.5 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; 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)

Air or MOV failure Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 90 ID: 2169443 Points: 1.00

1. Why does 1BOSR 6.6.2-1 REACTOR CONTAINMENT FAN COOLER SURVEILLANCE, specify the "AS LEFT" RCFC SX flow to be >5% ABOVE the Tech Spec limit?

2. Why does 1BOSR 6.6.2-1 specify a MAXIMUM flow for each RCFC bank?

A. 1. To account for instrument inaccuracies.

2. To indicate possible leaking RCFC tubes.

B. 1. To account for instrument inaccuracies.

2. To prevent exceeding flow velocities limits in the RCFC tubes.

C. 1. To account for changing system operation of the SX towers.

2. To indicate possible leaking RCFC tubes.

D. 1. To account for changing system operation of the SX towers.

2. To prevent exceeding flow velocities limits in the RCFC tubes.

Answer D Answer Explanation A - Incorrect: Plausible because instrument inaccuracies (tolerances) are typically accounted for in the surveillance requirements and safety analysis. Also plausible because other cooling water systems have high flow interlocks which would be indicative of system leaks such as CC to containment penetration cooling.

B - Incorrect: Plausible because instrument inaccuracies (tolerances) are typically accounted for in the surveillance requirements and safety analysis.

C - Incorrect: Plausible because other cooling water systems have high flow interlocks which would be indicative of system leaks such as CC to containment penetration cooling.

D - Correct: Per 1BOSR 6.6.2-1 and Tech Spec 3.6.6, the minimum flow requirement per RCFC is 2660 gpm (2 bank total for RCFC). A note in the surveillance reads the following:

A 5% margin is applied such that (2660 gpm + margin tolerance) equates to 2800 gpm to allow daily system operation including operation of the SX towers with a minimum of 4 risers open to maintain RCFC flow above Tech Spec flow of 2660 gpm. "As Left" RCFC SX flow shall be VERIFIED/ADJUSTED > 2800 gpm prior to completion of this surveillance.

Individual RCFC banks upper flow limit is limited to 1700 gpm to prevent exceeding flow velocity limits per IR 1096357.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q90 User ID SS20076-N02 System ID 2169443 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # 1BOSR 6.6.2-1 Rev. 35 Training Objective S.VP1-10 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of surveillance procedures.

SRO-Only Justification The question is SRO ONLY because it requires information contained in TS 3.6.6 bases document and surveillance requirements.

Additional Information None 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)

P2.2.12 Safety Function 4 Tier 3 Group RO Imp: 3.7 SRO Imp: 4.1 Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 91 ID: 2212166 Points: 1.00

An RCS cooldown and depressurization are in progress per 1BEP ES-0.2, NATURAL CIRCULATION COOLDOWN.

Charging and letdown flow are approximately equal.

RVLIS is available.

The RCS cooldown rate is 25oF/hr.

As RCS pressure is lowered through 1300 psig, a rapid rise in PZR level is observed.

There are currently NO time restrictions for RCS cooldown or depressurization.

1. What does the PZR level rise indicate?

2. What action should be taken?

A. 1. Natural circulation has stopped.

2. Go to 1BEP ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS) and raise RCS cooldown rate.

B. 1. Natural circulation has stopped.

2. Go to 1BEP ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS) and raise RCS pressure.

C. 1. The reactor head is voiding.

2. Remain in 1BEP ES-0.2 and raise the RCS cooldown rate.

D. 1. The reactor head is voiding.

2. Remain in 1BEP ES-0.2 and raise RCS pressure.

Answer D Answer Explanation A is incorrect, pressurizer level is not an indication used for natural circ conditions and raising the cooldown rate would likely raise the void growth. Plausible because this is a condition that is likely during 1BEP ES-0.2. Plausible, however transition to 1BEP ES-0.3 is only made if the RCS depressurization must continue. Because there are no restrictions on the depressurization time, the transition will not be made.

B is incorrect, pressurizer level is not an indication used for natural circ conditions, Plausible because this is a condition that is likely during 1BEP ES-0.2. Plausible, however transition to 1BEP ES-0.3 is only made if the RCS depressurization must continue. Because there are no restrictions on the depressurization time, the transition will not be made.

C is incorrect, raising the cooldown rate would likely raise the void growth. Plausible because raising the cooldown rate is a strategy for inactive loops during 1BEP ES-0.2.

D is correct, Rapid pressurizer level changes are indication that vessel head voids are forming due to a reduction in vessel head bypass flow. 1BEP ES-0.2, step 17 has the operator repressurize the RCS to collapse potential voids.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q91 User ID SS20002-N01 System ID 2212166 Status Active Point Value 1.00 Time (min) 2 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # 1BEP ES-0.2 Rev. 302 Training Objective T.EP01-06-D Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to predict impact on the RCS during operations with loss of forced flow.

SRO-Only Justification The question is SRO ONLY because it requires detailed procedure knowledge not contained in notes, cautions, OAS or CAS.

Additional Information From Bwd 2009 NRC exam K/A Reference(s)

SF2.002.A2.03 Safety Function 2 Tier 2 Group 2 RO Imp: 4.1 SRO Imp: 4.3 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; 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)

Loss of forced circulation Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 210 of 229

2021 RO/SRO NRC Exam Test Key Question 92 ID: 2169445 Points: 1.00

Unit 1 is at 100% power.

1LI-RC019, RVLIS Channel A, was declared INOPERABLE 60 days ago and will not be repaired until the next refuel outage scheduled in 6 months.

All actions of Tech Spec 3.3.3 have been completed for the failure of 1LI-RC019.

Subsequently the following occurs:

1LI-501A, S/G 1A Wide Range Water Level, is declared INOPERABLE.

Assuming 1LI-501A remains INOPERABLE indefinitely, what is the Tech Spec required action?

[REFERENCE PROVIDED]

A. Enter Tech Spec 3.0.3 IMMEDIATELY and perform the required actions of Tech Spec 3.0.3.

B. After 7 days initiate action in accordance with Specification 5.6.7.

C. After 7 days be in Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND be in Mode 4 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D. After 30 days initiate action in accordance with Specification 5.6.7.

Answer C Answer Explanation A - Incorrect: Plausible because there is no condition in TS 3.3.3 for both failures being concurrent.

Normally concurrent failures with no TS condition requires a TS 3.0.3 entry. However, TS 3.3.3 contains a note that allows separate condition entry for each function in the table. Therefore TS 3.0.3 entry is not required.

B - Incorrect: Plausible because condition E for two or more required channels inoperable requires a 7 day completion time for return to operable status and then an entry into condition G for TS 5.6.7 actions.

However, the 2 inoperable channels must be in the same function to make condition E applicable.

C - Correct: SG Wide Range Level channels have only 1 channel available and 1 channel required per LCO 3.3.3. Per condition D, a single channel inoperable for >7 days would require entry into condition F and Mode 3 entry within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Mode 4 entry within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D - Incorrect: Plausible because condition B (which is applicable to the previously failed RVLIS channel) requires a 30 day completion time for return to operable status and then an entry into condition C for TS 5.6.7 actions.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q92 User ID SS20016-N01 System ID 2169445 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number OPEN Cognitive Level SRO-HIGH Operator Discipline LO-I CFR: 43.2 Facility operating limitations in the technical specifications and 10CFR55 Content their bases.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # TS 3.3.3 Amendment 141/143 Training Objective S.TS1-12 Previous 2 Byron NRC Exams Use None References Provided Tech Spec LCO 3.3.3 K/A Justification Question meets the K/A, requires examinee ability to apply Tech Spec for various system non-nuclear instrumentation.

SRO-Only Justification The question is SRO ONLY because it requires ability to apply tech specs that are not 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or less completion times.

Additional Information None K/A Reference(s)

GS.3.0.SF7.016 Safety Function 7 Tier 2 Group 2 RO Imp: SRO Imp:

Non-Nuclear Instrumentation System (NNIS)

P2.2.40 Safety Function 7 Tier 3 Group RO Imp: 3.4 SRO Imp: 4.7 Ability to apply Technical Specifications for a system.

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 93 ID: 2169446 Points: 1.00

Unit 1 is at 100% power.

1BOSR MS-Q1, STEAM DUMP VALVE OPERABILITY QUARTERLY SURVEILLANCE, is in progress.

During the stroke test of 1MS004C, STEAM DUMP VALVE, the valve stuck OPEN and would not re-close.

The US directed the crew to MAINTAIN 1MS003C, STEAM DUMP VALVE UPSTREAM MANUAL ISOLATION VALVE, CLOSED and complete the surveillance for all the other steam dump valves.

1BOSR MS-Q1 has been completed (with 1MS003C left CLOSED), and it was noted the acceptance criteria was not met for 1MS004C.

1. What steam dump demand signal range would 1MS004C have normally begun to open?

2. How will the US track the position of the manual isolation valve, 1MS003C?

A. 1. 0% to 50%

2. Equipment Status Tag (EST) Log B. 1. 0% to 50%

2. Degraded Equipment Log (DEL)

C. 1. 51% to 100%

2. Equipment Status Tag (EST) Log D. 1. 51% to 100%

2. Degraded Equipment Log (DEL)

Answer C Answer Explanation A is incorrect, 0% to 50% is a plausible distractor considering the unusual grouping of the valves and that their MCR indication is laid out alphabetically (vs. by their respective group).

B is incorrect, 0% to 50% is a plausible distractor considering the unusual grouping of the valves and that their MCR indication is laid out alphabetically (vs. by their respective group).

The degraded equipment log is a plausible distractor as it would be used for a similar purpose if the malfunction was on an SSC that is safety related.

C is correct, The steam dump stroke surveillance consists of locally isolating the steam dumps and then manually stroking them from the MCR. When a valve is stuck open the local manual isolation valve is maintained closed to prevent steam flow through the failed open valve. The steam dumps valves are divided into four groups that open sequentially (by group) as demand rises from 0% to 100%. The valves are grouped as follows:

Group 1 Group 2 Group 3 Group 4 Valves A, E & J B, F & K C,G & L D, H & M Demand signal 0%-25% 26%-50% 51%-75% 76%-100%

The C steam dump valve is in group 3 and opens on demand of 51%-75%.

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2021 RO/SRO NRC Exam Test Key The correct tracking mechanism is the Equipment Status Log, which tracks equipment status tags that identify temporary status of equipment position to ensure configuration control per OP-AA-108-101.

D is incorrect, The degraded equipment log is a plausible distractor as it would be used for a similar purpose if the malfunction was on an SSC that is safety related.

Question Information Topic 2021 NRC Q93 User ID SS20041-N02 System ID 2169446 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-HIGH Operator Discipline LO-I CFR: 43.3 Facility licensee procedures required to obtain authority for 10CFR55 Content design and operating changes in the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # OP-AA-108-101 Rev. 15 Training Objective T.AM35-08 Byron Previous 2 NRC Exam Use None References Provided None K/A Justification The question meets the K/A because the candidate must predict the results of a loss of a steam dump and use procedures to control the effects of the malfunction.

SRO-Only Justification The question is SRO level because the admin processes for equipment control are SRO functions at Byron per the exam facilty representative SRO.

Per OP-AA-108-101, Control of Equipment and System Status, the operations Unit Supervisor has responsibility for authorizing installation and removal of TCCs, controlling TCC tag numbers and tags, and entering required information into the TCC Tracking Log.

Additional Information From Bwd 2016 NRC Exam K/A Reference(s)

SF4.041.A2.02 Safety Function 4 Tier 2 Group 2 RO Imp: 3.6 SRO Imp: 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.13)

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2021 RO/SRO NRC Exam Test Key Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 215 of 229

2021 RO/SRO NRC Exam Test Key Question 94 ID: 2169447 Points: 1.00 During fuel moves within the reactor vessel, which of the following is NOT the Licensed SRO fuel handling supervisor responsibility?

A. Approve changes to the move sheet.

B. Control of access to the refuel floor areas.

C. Perform visual core alignment inspection.

D. Maintain direct communications with the Control Room.

Answer A Answer Explanation A - Correct: Per OU-AP-200 section 2.5 this is the responsibility of the Reactor Engineer.

B - Plausible: Item 15 under Reactor Services Supervisor designates responsibility for access control to the refueling areas (and item 3.2.5 assigns the SRO the same responsibilities as the Reactor Services Supervisor when supervising fuel related activity). This is a valid distractor because it can be performed by the Reactor Services Supervisor when an SRO is not on the refuel floor.

C - Plausible: OU-AP-200 section 3.2.4 and NF-AA-330-1001 section 3.5 designate SRO responsibility for visual core alignment inspection. This is a valid distractor because it is a task that must be performed from the refuel floor.

D - Plausible: OU-AP-200 section 3.2.3 designates the SRO responsibility for maintaining direct communication with the MCR. This is a valid distractor because it is a task that must be performed from the refuel floor.

Question Information Topic 2021 NRC Q94 User ID SG32142-N01 System ID 2169447 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I 10CFR55 Content CFR: 43.7 Fuel handling facilities and procedures.

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2021 RO/SRO NRC Exam Test Key Question Type Bank Difficulty Technical Reference and Revision # OU-AP-200 Rev. 24 Training Objective T.AM12-16 Byron Previous 2 NRC Exam Use None References Provided None K/A Justification Meets K/A, requires examinee knowledge of SRO fuel handling responsibilities per OU-AP-200 (fuel handling administrative procedure).

SRO-Only Justification SRO only because it is specific knowledge of the SRO duties.

Additional Information From 2020 Bwd NRC exam K/A Reference(s)

P2.1.35 Safety Function 4 Tier 3 Group RO Imp: 2.2 SRO Imp: 3.9 Knowledge of the fuel-handling responsibilities of SROs.

(CFR: 41.10 / 43.7)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 95 ID: 2169448 Points: 1.00 Who is responsible to evaluate EMERGENT on-line risk prior to plant configuration changes?

A. Site Risk Engineer B. Work Week Manager C. Unit Supervisor D. Shift Manager Answer C Answer Explanation A - Incorrect: Plausible because the Site Risk Management Engineer serves as the site lead for all risk management activities and provides technical guidance to operations application of risk tools.

B - Incorrect: Plausible because the Work Week Manager performs planned risk assessments for work schedule activities. Also, OP-AA-101-111 instructs the SRO to keep the Work Week Manager informed of any risk significant configuration changes.

C - Correct: Per OP-AA-101-111, ROLES AND RESPONSIBILITIES OF ON SHIFT PERSONNEL, step 4.2.6 the Unit Supervisor is responsible for emergent risk assessments.

D - Incorrect: Plausible because OP-AA-101-111 instructs the SRO to keep the Shift Manager informed of any risk significant configuration changes.

Question Information Topic 2021 NRC Q95 User ID SG10039-N01 System ID 2169448 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I CFR: 43.3 Facility licensee procedures required to obtain authority for 10CFR55 Content design and operating changes in the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # OP-AA-101-111 Rev. 12 Test ID: 347808 09/15/2021 218 of 229

2021 RO/SRO NRC Exam Test Key Training Objective T.AM29-07 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of risk management process which supports the conservative decision making process by providing risk insights to be used in the operation of the plant.

SRO-Only Justification The question is SRO ONLY because emergent risk assessment is an SRO function. Per OP-AA-101-111, ROLES AND RESPONSIBILITIES OF ON SHIFT PERSONNEL, the Unit Supervisor is responsible for emergent risk assessments.

Additional Information None K/A Reference(s)

P2.1.39 Safety Function 4 Tier 3 Group RO Imp: 3.6 SRO Imp: 4.3 Knowledge of conservative decision making practices.

(CFR: 41.10 / 43.5 / 45.12)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 219 of 229

2021 RO/SRO NRC Exam Test Key Question 96 ID: 2169449 Points: 1.00 Both Units are at 100% reactor power.

You are reviewing the work schedule for the following day and notice a maintenance activity that requires removal of a system from service that will change on-line risk level to RED.

Per WC-AA-101, ON-LINE WORK CONTROL PROCESS, what guidance is given for the activity?

A. The maintenance activity must be performed around the clock.

B. The voluntary removal of the system from service is NOT permitted.

C. Protected equipment and pathways must be posted before maintenance may begin.

D. Maintenance may begin once all parts and materials are pre-staged at the work location.

Answer B Answer Explanation A - Plausible: required if Yellow risk level is entered.

B - Correct: per WC-AA-101 On-Line Work Control Process Attachment 3 Configuration Risk Management Criteria, it is unacceptable to voluntarily enter red risk level.

C - Plausible: required if Yellow or Orange risk levels are entered.

D - Plausible: required if Yellow or Orange risk levels are entered.

Question Information Topic 2021 NRC Q96 User ID SG20017-N02 System ID 2169449 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I CFR: 43.3 Facility licensee procedures required to obtain authority for 10CFR55 Content design and operating changes in the facility.

NRC Exams Only Question Type Bank Difficulty Test ID: 347808 09/15/2021 220 of 229

2021 RO/SRO NRC Exam Test Key Technical Reference and Revision # WC-AA-101 Rev. 31 section 4.19 Training Objective T.MC07-01 Byron Previous 2 NRC Exam Use None References Provided None K/A Justification This question meets the KA because the examinee must be knowledgeable of the process for managing maintenance activities to answer this question.

SRO-Only Justification It is an SRO job function to screen activities for risk and determine work authorization. Per WC-AA-101, Work Control Process, it is the responsibility of Operations shift management to ensure appropriate actions are taken to mitigate online risk.

Additional Information From Clinton 12-1 NRC exam K/A Reference(s)

P2.2.17 Safety Function 4 Tier 3 Group RO Imp: 2.6 SRO Imp: 3.8 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

(CFR: 41.10 / 43.5 / 45.13)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 97 ID: 2169450 Points: 1.00

An emergent priority troubleshooting work activity is in progress.

The initial troubleshooting did not identify the problem.

The maintenance crew has returned to the control room with new troubleshooting work instructions to further investigate the malfunction.

What is the Unit Supervisor's responsibility for this activity per MA-AA-716-004, CONDUCT OF TROUBLESHOOTING?

A. Lead the troubleshooting process.

B. Update the Maintenance Alteration Log.

C. Review and approve the new troubleshooting activity.

D. Document the troubleshooting results in the Troubleshooting Log.

Answer C Answer Explanation A. Incorrect: This activity is plausible as it can fall under the SM/Designee responsibility but is not listed as a US responsibility. (Reference step 3.6.1)

B. Incorrect: This is plausible as the maintenance alteration log will be updated though out the troubleshooting process but that update will made by the "field work group". This is annotated on step 4.1.10.3 of procedure MA-AA-716-004 C. Correct: Per MA-AA-716-004, (step 3.7.1) the Unit Supervisors responsibilities are to: Authorizes field troubleshooting activities and ensures adequate bounds have been established to limit plant impact and/or cause a change from previous risk assessment values by review and approval of each applicable Attachment 1, Troubleshooting Log.

D. Incorrect: Documentation in the troubleshooting log is normally performed by the maintenance crew but could be performed by operating, making this choice plausible.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q97 User ID SG20020-N01 System ID 2169450 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I CFR: 43.3 Facility licensee procedures required to obtain authority for 10CFR55 Content design and operating changes in the facility.

NRC Exams Only Question Type Bank Difficulty Technical Reference and Revision # MA-AA-716-004 Rev. 19 Training Objective T.AM30-03 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the troubleshooting process and what to do to manage a change to the troubleshooting field activities.

SRO-Only Justification The question is SRO ONLY because authorizing field troubleshooting activities is an SRO function per MA-AA-716-004.

Additional Information From Byron 2017 NRC exam K/A Reference(s)

P2.2.20 Safety Function 4 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) 2021 NRC Exam User (Sys) ID N/A (1554540)

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2021 RO/SRO NRC Exam Test Key Question 98 ID: 2169451 Points: 1.00

A Gas Decay tank release is pending.

The SRO is filling out BCP 400-EWASTE GAS, GASEOUS EFFLUENT RELEASE FORM TYPE:

WASTE GAS DECAY TANK, and evaluating whether to approve the release with the current exhaust fan configuration.

What is the REQUIRED VA EXHAUST fan alignment to perform the waste gas decay tank release?

A. MUST have at least 1 exhaust fan running on EACH Unit. (minimum of 2 fans running)

B. MUST have 1 exhaust fan running on EITHER Unit. (minimum of 1 fan running)

C. MUST have 1 exhaust fan running (0A or 0B) on UNIT 1. If ONLY a UNIT 2 exhaust fan (0C or 0D) is running the release CANNOT proceed.

D. MUST have 1 exhaust fan running (0C or 0D) on UNIT 2. If ONLY a UNIT 1 exhaust fan (0A or 0B) is running the release CANNOT proceed.

Answer B Answer Explanation A - Incorrect: Plausible because this is the VA exhaust fan configuration for normal plant operations.

B - Correct: Per BCP 400-EWASTE GAS, any single VA exhaust fan in operation is adequate to perform the release. The waste gas release header merges with the filtered vent header and is connected to the Aux Building exhaust plenum upstream of the VA exhaust fans. All four fans take suction from a common plenum, and discharge to unit specific plenums that then exhaust to the unit specific plant vent stacks.

Therefore, any one fan will provide ample flow to the Unit 1 (0A or 0B fan) or Unit 2 (0C or 0D fan) Vent Stack.

C - Incorrect: Plausible because most plant equipment that has ducted exhaust ventilation (other than general area ventilation) connects with the unit specific exhaust plenums downstream of the Aux Building exhaust fans. In the case of containment releases, the exhaust fan configuration must match the unit containment that is being vented because the VQ system discharges downstream of the VA exhaust fans.

D - Incorrect: Plausible because most plant equipment that has ducted exhaust ventilation (other than general area ventilation) connects with the unit specific exhaust plenums downstream of the Aux Building exhaust fans. In the case of containment releases, the exhaust fan configuration must match the unit containment that is being vented because the VQ system discharges downstream of the VA exhaust fans.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q98 User ID SG30006-N02 System ID 2169451 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I CFR: 41.13 Procedures and equipment available for handling and disposal 10CFR55 Content of radioactive materials and effluents.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # BCP 400-EWASTE GAS Rev. 1 Training Objective 3S.GW-01 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee ability to approve radioactive releases by knowing the required ventilation fan configuration for the release.

SRO-Only Justification The question is SRO ONLY because it is the SRO function to approve the gas decay tank release and to placard the MCR ventilation panel to prevent any vent fan configuration changes during the release per BCP 400-EWASTE GAS.

Additional Information None K/A Reference(s)

P2.3.6 Safety Function 4 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) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 225 of 229

2021 RO/SRO NRC Exam Test Key Question 99 ID: 2169452 Points: 1.00 Concerning the Byron Functional Restoration (BFR) procedures:

1. What type of procedures are the BFRs?

2. What is the bases for priority of the BFRs?

A. 1. DESIGN BASIS EVENT procedures

2. prioritized by importance to core damage frequency B. 1. DESIGN BASIS EVENT procedures

2. prioritized by probability of event occurring per reactor years of operation C. 1. BARRIER CONCEPT procedures that address symptoms

2. protecting containment is the FIRST priority D. 1. BARRIER CONCEPT procedures that address symptoms

2. protecting fuel cladding is the FIRST priority Answer D Answer Explanation A - Incorrect: Plausible because BEP and BCAs procedures are event based procedures and systems are rated in PRA according to their importance to core damage frequency.

B - Incorrect: Plausible because BEP and BCA procedures are event based procedures and the events in each procedure group are separated by probability of occurring less than (or greater than) 10-8 per reactor year of operation.

C - Incorrect: Plausible because second part of answer is opposite of the correct answer.

D - Correct: Per WOG ERG Executive Summary and BAP 1310-10, BFRs are barrier based procedures and the priority is based upon the relationship of the fission product barrier (each procedure is designed to protect) to the environment. The fission product barriers are in order (of potential release):

1. Fuel matrix and cladding

2. RCS integrity

3. Containment integrity The BST priority of SCHPZI is designed to protect the barriers in that order.

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q99 User ID SG40023-N01 System ID 2169452 Status Active Point Value 1.00 Time (min) 0 Cross Reference Number CLOSED Cognitive Level SRO-LOW Operator Discipline LO-I CFR: 41.10 Administrative, normal, abnormal, and emergency operating 10CFR55 Content procedures for the facility.

NRC Exams Only Question Type New Difficulty Technical Reference and Revision # Background Information for WOG ERG F-0 Critical Safety Function Status Trees Rev. 3, BAP 1310-10 Rev. 21 Training Objective T.EP00-07 Previous 2 Byron NRC Exams Use None References Provided None K/A Justification Question meets the K/A, requires examinee knowledge of the bases for prioritizing emergency procedures.

SRO-Only Justification The question is SRO ONLY because monitoring of the Status Trees is normally performed by the STA per BAP 1310-10, HU-AA-104-101, PROCEDURE USE AND ADHERENCE, BYRON ADDENDUM Additional Information None K/A Reference(s)

P2.4.23 Safety Function 4 Tier 3 Group RO Imp: 3.4 SRO Imp: 4.4 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

(CFR: 41.10 / 43.5 / 45.13)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 227 of 229

2021 RO/SRO NRC Exam Test Key Question 100 ID: 2169453 Points: 1.00

Unit 1 was at 100% power when an automatic reactor trip and safety injection occurred.

A General Emergency has been declared based upon abnormal rad levels.

Containment is intact (NO loss per EALs).

Security reports all security conditions are normal.

There have been no reports received from the State of Illinois.

The wind direction is from 045°.

The Shift Emergency Director is assessing the INITIAL PARS recommendation from the MCR.

What is the INITIAL PARS recommendation?

[REFERENCE PROVIDED]

A. SHELTER 5 mile radius in Sub Areas 17, 19, 20, 23 and 25 B. SHELTER 2 mile radius and 5 miles downwind in Sub Areas 19, 20 and 23 C. EVACUATE 2 mile radius and 5 miles downwind in Sub Areas 19, 20 and 23 D. EVACUATE 2 mile radius and 10 miles downwind in Sub Areas 12, 14, 19, 20 and 23 Answer C Answer Explanation A is incorrect: Plausible because this is the Shelter requirement if a hostile action event was in progress (TABLE 2).

B is incorrect: Plausible because this is the Shelter requirement if PARS was not being made from the control room and a release via a controlled vent (and associated criteria) was made (Table 4). Byron does not have a controlled containment vent, but an error in the PARS flow chart could result in the candidate selecting this option.

C is Correct: PAR evaluation requires evacuation of the down wind sectors, The listed sectors are from Table 3 and Table B of the EP-AA-111-F-03.

D is incorrect: Plausible because this is the Evacuation requirement if a loss of containment event was in progress (TABLE 1).

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2021 RO/SRO NRC Exam Test Key Question Information Topic 2021 NRC Q100 User ID SG40044-N01 System ID 2169453 Status Active Point Value 1.00 Time (min) 3 Cross Reference Number OPEN Cognitive Level SRO-HIGH Operator Discipline LO-I 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 Technical Reference and Revision # EP-AA-111-F-03 Rev. J Training Objective T.ZP1-31 Previous 2 Byron NRC Exams Use None References Provided EP-AA-111-F03 K/A Justification Question meets the K/A, requires examinee knowledge of how to correctly use the PAR flowchart.

SRO-Only Justification The question is SRO ONLY because determining PARS recommendation is the responsibility of the Shift Emergency Director (SM or designee) per EP-AA-113, Personnel Protective Actions.

Additional Information From 2014 Byron NRC exam K/A Reference(s)

P2.4.44 Safety Function 4 Tier 3 Group RO Imp: 2.4 SRO Imp: 4.4 Knowledge of emergency plan protective action recommendations.

(CFR: 41.10 / 41.12 / 43.5 / 45.11)

Learning Objective(s) 2021 NRC Exam User (Sys) ID N/A (1554540)

Cross Reference Links None Test ID: 347808 09/15/2021 229 of 229

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