ML16111A524

2016 Prairie Island Nuclear Generating Plant Initial License Examination Proposed Written Exam

ML16111A524
Person / Time
Site:	Prairie Island
Issue date:	06/10/2016
From:	Mcneil D NRC/RGN-III/DRS/OLB
To:
References
L-PI-16-024
Download: ML16111A524 (134)

Text

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 001 The crew is on step 2 of 1E-0, Reactor Trip or Safety Injection.

CS-46427, TURB TRIP, has been depressed.

The Turbine is (1) and, upon completion of step 2 of 1E-0, MSIVs will be (2).

a. TRIPPED; (2) OPEN

b. TRIPPED; (2) CLOSED

c. NOT TRIPPED; (2) OPEN

d. NOT TRIPPED; (2) CLOSED ANSWER:

D

REFERENCE:

1E-0 pg 3 NEW HIGHER K/A: 007A107: Ability to operate and monitor the following as they apply to a reactor trip:

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY MT/G trip; verification that the MT/G has been tripped.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes the turbine is tripped with only one stop valve closed and therefore, the MSIVs would not need to be closed.

b. Incorrect. Plausible as MSIVs will be closed and if examinee incorrectly believes the turbine is tripped with only one stop valve closed.

c. Incorrect. Plausible as the turbine is not tripped and if examinee incorrectly believes MSIVs will still be open because at least one stop valve is closed.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-224 Obj. 42. P8197L-011 235

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 002 A Unit 1 Pressurizer PORV fails OPEN.

Unit 1 reactor is tripped.

Unit 1 Safety Injection is actuated.

Both Safety Injection pumps are running with flow indicated.

RCS pressure is 1200 psig and lowering.

The crew (1) stop both Reactor Coolant Pumps in order to MINIMIZE (2).

a. WILL; (2) RCS cooldown

b. WILL; (2) depletion of RCS inventory

c. WILL NOT; (2) RCS cooldown

d. WILL NOT; (2) depletion of RCS inventory ANSWER: B

REFERENCE:

1E-0 Bases, page 4.

NEW HIGHER K/A: 008A222: Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: Consequences of loss of pressure in RCS; methods for evaluating pressure loss.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes the reasons for stopping RCPs, when trip criteria are met, is for minimizing RCS cooldown.

b. Correct. PRZR steam space accident is considered a SBLOCA. RCPs must be stopped during SBLOCAs to prevent RCS inventory depletion to the point where tripping of the pumps at a later time would result in immediate uncovering of the core.

c. Incorrect. Plausible if examinee incorrectly believes RCP trip criteria is not met; also incorrectly believes trip criteria is based on minimizing cooldown because RCPs are a heat source for the RCS.

d. Incorrect. Plausible as RCS inventory depletion is the primary concern for RCP trip criteria and if examinee incorrectly believes that keeping RCPs running is necessary to prevent void formation in the core and subsequent core uncovering.

Proposed references to be provided to applicants during examination: None.

Learning Objective: P8197L-011 Obj A

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 003 A small break LOCA has occurred on Unit 1.

The crew is on step 11 of 1E-1, Loss of Reactor or Secondary Coolant, to determine if Safety Injection flow should be terminated.

RCS subcooling is 87°F.

RCS pressure is 2200 psig and rising.

11 and 12 Steam Generator narrow range levels are 25% and stable.

Pressurizer level is 31% and stable.

Will the Reactor Operator stop RHR and/or SI pumps?

RHR SI

a. NO NO

b. NO YES

c. YES NO

d. YES YES ANSWER:

D

REFERENCE:

1E1 pg 6 NEW HIGHER K/A: 009 2.1.7: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that break has not been isolated.

b. Incorrect. Plausible if examinee incorrectly believes that SI flow refers only to SI pumps.

c. Incorrect. Plausible if examinee believes that RHR should be secured per step 12 of 1E-1.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-233 Obj. B.3

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 004 A LOCA occurred on Unit 1.

Core Exit Thermocouples are 300°F and slowly lowering.

RCS pressure is slightly higher than containment pressure.

SG pressures are 675 psig and slowly lowering.

(1) Heat removal is occurring by (1). (2) Heat removal will be continued by maintaining (2).

a. break flow ONLY; (2) at least the minimum necessary ECCS injection flow

b. break flow ONLY; (2) SG NR level using aux feed, and reducing steam pressure using SG PORVs or Steam Dumps to the condenser if available

c. reflux cooling ONLY; (2) SG NR level using aux feed, and reducing steam pressure using SG PORVs or Steam Dumps to the condenser if available

d. reflux cooling ONLY; (2) at least the minimum necessary ECCS injection flow ANSWER:

A

REFERENCE:

USAR App K, pg. K-5 BANK HIGHER K/A:011K1.01: Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.

EXPLANATION:

The maximum containment pressure under any circumstances during a LBLOCA is expected to be less than 50 PSIG. Under these conditions, the RCS has completely blown down, and ECCS is expected to be cooling the core then spilling out of the break. Two-phase cooling will only occur if the SGs are still a heat sink. In this case the SG saturation temperatures are about 200°F greater than the Core exit temperatures, such that the SGs are actually a heat source.

The only operator response to aid in core cooling is to continue to follow the ERGs and maintain core cooling using ECCS.

JUSTIFICATION:

a. Correct. See EXPLANATION above.

b. Incorrect. Plausible if the applicant has a misconception about the conditions given, and procedural guidance as to the basis and timing for reducing SG pressure following a LBLOCA.

c. Incorrect. Plausible if the applicant has a misconception of the mechanisms for two-phase cooling. Could be correct if reflux cooling were occurring.

d. Incorrect. Plausible if the applicant has a misconception of the mechanisms for two-phase cooling, or core cooling during a LBLOCA vs. SBLOCA.

Proposed references to be provided to applicants during examination: None Learning Objective: P8188L-003 Obj. 1E

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 005 Unit 2 is in MODE 3.

A loss of Unit 2 Component Cooling has occurred.

21 RCP has been stopped.

The Reactor Operator will maintain flow after the RCP is stopped.

a. lift oil

b. seal bypass

c. seal injection

d. pressurizer spray ANSWER:

C

REFERENCE:

C3 pg 19 NEW MEMORY K/A: 015/017K2.07: Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP seals.

Justification:

a. Incorrect. Plausible if the examinee believes the RCP lift oil pump auto starts on a RCP trip similar to the main turbine lift oil pump.

b. Incorrect. Plausible if the examinee believes that seal bypass could be used to provide additional cooling during a loss of CC in this mode.

c. Correct.

d. Incorrect. Plausible if the examinee believes that the mixing must continue to prevent a reactivity change when the pump is restarted.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-002 Obj. 6

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 006 Unit 1 is in Mode 5.

RHR Train B is aligned for shutdown cooling.

PNL 112, INSTR BUS 1 (RED) PNL 112, is de-energized.

The crew will...

a. shift to RHR Train A because CV-31236 failed OPEN.

b. shift to RHR Train A because CV-31237 failed CLOSED.

c. place 1HC-626A in manual because CV-31236 failed OPEN.

d. place 1HC-626A in manual because CV-31237 failed CLOSED.

ANSWER:

A

REFERENCE:

1C15 AOP1 pg 6 NEW HIGHER K/A: 025K3.01: Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Shift to alternate flowpath.

JUSTIFICATIONS:

a. Correct.

b. Incorrect. Plausible if the examinee incorrectly believes CV-31237 is powered by the red

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY bus.

c. Incorrect. Plausible because CV-31236 failure will impact CV-31327 position if the examinee incorrectly believes the response to this failure is to take manual control of the bypass.

d. Incorrect. CV-31237 is not in its normal position for this situation. This is plausible if the examinee incorrectly believes that this valve has failed rather than the position change having been caused by the CV-31236 failure.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 007 Unit 1 is at 100% power.

1R-39, Component Cooling System Liquid Monitor, is in HIGH ALARM.

Annunciator 47020-0203, 11 CC SURGE TANK HI/LO LEVEL, is in alarm.

What is the status of CV-31432, 11 CC SURGE TANK MAKEUP CONTROL VALVE, and MV-32088, 11 CC SURGE TANK VENT?

CV-31432 MV-32088 11 CC SURGE TANK 11 CC SURGE MAKEUP CONTROL VALVE TANK VENT

a.

OPEN OPEN

b.

OPEN CLOSED

c.

CLOSED OPEN

d.

CLOSED CLOSED ANSWER:

D

REFERENCE:

1C14 AOP2 pg 3 C47020-0203 BANK HIGHER K/A: 026A105: Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water: The CCWS surge tank, including level control and level alarms, and radiation alarm.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that surge tank level is lowering and 1R-39 has no automatic actions.

b. Incorrect. Plausible if examinee incorrectly believes that surge tank level is lowering.

c. Incorrect. Plausible if examinee incorrectly believes 1R-39 has no automatic actions.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-002 Obj. 3.A.4.f

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 008 Rod control is in MANUAL.

AMSAC/DSS is Out of Service.

CS-46450, REACTOR TRIP TRIP-RESET TRAINS A AND B, is momentarily taken to the TRIP position.

CS-46331, REACTOR TRIP TRAINS A AND B, is momentarily taken to the TRIP position.

The Reactor Operator observes the following:

(1) Is the reactor subcritical?

(2) Will the Reactor Operator manually insert control rods?

Reactor Manually Insert Subcritical Control Rods

a.

YES YES

b.

YES NO

c.

NO YES

d.

NO NO ANSWER C

REFERENCE:

1FR-S.1 pg 3 NEW

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY HIGHER K/A:029A201: Ability to determine or interpret the following as they apply to a ATWS:

Reactor nuclear instrumentation.

JUSTIFICATION:

a. Incorrect. Plausible if student believes that startup rate is indicating a subcritical reactor.

b. Incorrect. Plausible if student believes that startup rate is indicating subcritical and therefore, rods do not need to be inserted.

c. Correct.

d. Incorrect. Plausible if student believes that startup rate indicated does not require rod insertion but that power level indicates that the reactor is critical.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-229 Obj. 5

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 009 Information page actions of 1ECA-2.1, Uncontrolled Depressurization of Both Steam Generators, (1) continuous action steps and (2) performed from memory.

(1) are; (2) are (1) are; (2) are NOT (1) are NOT; (2) are (1) are NOT; (2) are NOT ANSWER B

REFERENCE:

SWI O-10, page 10 NEW MEMORY K/A:E12 2.4.21: Knowledge of general operating crew responsibilities during emergency operations.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that info page steps do not need to be re-read once the procedure has been entered.

b. Correct.

c. Incorrect. Plausible if the examinee incorrectly believes that reference use sections within the continuous use procedure.

d. Incorrect. Plausible if the examinee incorrectly believes that information page steps can only be performed upon entry into the EOP.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007, Obj. 4.C.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 010 A Main Feedwater Line Break has occurred on Unit 1.

Containment pressure is 0 psig and stable.

11 Steam Generator is 795 psig and slowly lowering.

11 Steam Generator is 55% WR level and stable.

12 Steam Generator is 695 psig and slowly lowering.

12 Steam Generator is 50% WR level and stable.

The Main Feedwater line break is in the (1) Building and is (2) of the Main Feedwater line check valve.

(1) Auxiliary; (2) upstream (1) Auxiliary; (2) downstream (1) Containment; (2) upstream (1) Containment; (2) downstream ANSWER A

REFERENCE:

B28A, pages 12, 23 MODIFIED HIGHER K/A:054K1.01: Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break)

JUSTIFICATION:

a. Correct. A break upstream of the FW check valves would not allow either SG to empty, and since the check valves are located inside CTMT on the CTMT wall, the break would have to be in the AB.

b. Incorrect. Plausible as the break is in the AB and if examinee incorrectly confuses the location and function of the check valve in the system.

c. Incorrect. Plausible as the break is upstream of the check valve and if examinee incorrectly confuses the location of the check valve.

d. Incorrect. Plausible if examinee incorrectly believes the check valve is outside of containment (similar to main steam non-return check valve) and incorrectly believes a downstream leak would cause the given indications.

Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-003 Obj. 6B

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 011 The crew is performing 1ECA-0.0, Loss of All Safeguards AC Power.

An out-plant operator has been dispatched to isolate RCP seals.

CC-16-2 and CC-16-3, RCP CC return isolation valves, are CLOSED to prevent...

a. overfilling the 11 Component Cooling Surge Tank.

b. overfilling the VCT due to seal return relief valve lifting.

c. seal return flow from diverting to the PRT via relief valve.

d. steam formation in the CC System due to RCP thermal barrier heating.

ANSWER D

REFERENCE:

1ECA-0.0, page 7, 1ECA-0.0 bases, page 5.

BANK MEMORY K/A: 055K3.02: Knowledge of the reasons for the following responses as they apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes RCS will leak into CC system with no charging pumps running.

b. Incorrect. Plausible if the examinee confuses the reasons for closing MV-32166 with the reasons for closing CC-16-2 and CC-16-3. MV-32166 is closed to prevent overfilling the VCT due to seal return relief valve lifting.

c. Incorrect. Plausible if the examinee confuses the OUTCOME of closing MV-32166 with the reasons for closing CC-16-2 and CC-16-3. Also, both refer to their respective system return lines.

d. Correct. Per 1ECA-0.0: Isolating the RCP CC return outside containment prepares the plant for recovery while protecting the CC system from steam formation due to RCP thermal barrier heating. Following the loss of all AC power, hot reactor coolant will gradually replace the normally cool seal injection water in the RCP seal area. As the hot reactor coolant leaks up the RCP shaft, the water in the thermal barrier will heat up and potentially form steam in the thermal barrier and in the CC lines adjacent to the thermal barrier. Subsequent automatic start of the CC pump would deliver CC flow to the thermal barrier, flushing steam into the CC system.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-011 Obj. F.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY

12. P8186L-008 54 A loss of offsite power occurs on Unit 1.

A Large Break LOCA occurs on Unit 1.

(1) What is the FIRST load that will START when Safeguards Bus voltage is restored?

(2) What is the reason for the TIME DELAY between load start signals on the Load Sequencer?

(1) Safety Injection pumps; (2) Allows sufficient time for safeguard bus voltage to recover between load starts.

(1) Safety Injection pumps; (2) Ensures full rated ECCS flow can be delivered within 20 seconds of a Safety Injection signal.

(1) 12 Motor Driven Auxiliary Feedwater pump; (2) Allows sufficient time for safeguard bus voltage to recover between load starts.

(1) 12 Motor Driven Auxiliary Feedwater pump; (2) Ensures full rated ECCS flow can be delivered within 20 seconds of a Safety Injection signal.

ANSWER A

REFERENCE:

USAR 8.4.3, pg. 8.4-9 NEW MEMORY K/A:056K3.01: Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Order and time to initiation of power for the load Sequencer.

JUSTIFICATION:

a. Correct. Synchronous drive motors require 3-4 seconds to reach full speed, allowing high starting currents to lower to running current. USAR 8.4 states 5 seconds have been shown to be a sufficient time for bus voltage to return to 100% after a load start.

b. Incorrect. Plausible as SI pumps are first to start and the full flow within 20 seconds is a reason for the ORDER of load restoration; however, the question is asking for reasons for the TIME DELAY.

c. Incorrect. Plausible if examinee incorrectly believes AFW is required to maintain a heat sink BEFORE starting a core cooling injection pump.

d. Incorrect. Plausible if examinee incorrectly believes AFW is required to maintain a heat sink BEFORE starting a core cooling injection pump; also because the full flow within 20 seconds is a reason for the ORDER of load restoration; however, the question is asking for reasons for the TIME DELAY.

Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-008 Obj. 9A

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 013 CS-46291, PRZR LEVEL CONTROL CHANNEL SEL, is in the 2-3 (white-blue) position.

Annunciator 47005-0307, PNL 113 INSTR BUS III (BLUE) LOSS OF VOLTAGE, is in alarm.

The following is a list of potential actions to place the charging pump speed controller in MANUAL control:

1. Place the transfer switch in the MANUAL position.

2. Adjust the BIAS dial to the zero output on the output meter.

3. Place the transfer switch in the AUTO-BALANCE position.

4. Adjust the BIAS dial for zero deviation on the deviation indicator.

5. Adjust the MANUAL control knob for zero deviation on the deviation indicator.

List the steps required in the correct order to transfer the charging pump speed controller to MANUAL control per C7, Reactor Control System.

a. 1 2

b. 3 1

c. 3 1 - 5

d. 4 2 - 5 ANSWER B

REFERENCE:

C7 pg. 10 NEW

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY MEMORY K/A: 057A1.06: Ability to operate and/or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual control of components for which automatic control is lost.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that the manual control knob is only used when the charging pump is already in manual control.

b. Correct.

c. Incorrect. Plausible if the examinee incorrectly believes that the manual balance position is correct as manual control is the desired end state and the manual control knob is only used when in manual control.

d. Incorrect. Plausible if the examinee incorrectly believes that the manual balance position is correct as manual control is the desired end state.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-222 Obj 5

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 014 Unit 1 Instrument Air header pressure is lowering.

Operators are responding per C34 AOP1, Loss of Instrument Air.

Which parameter will be the FIRST to require initiation of a reactor trip?

a. Rising RCP temperatures.

b. Lowering pressurizer level.

c. Rising pressurizer pressure.

d. Lowering steam generator levels.

ANSWER D

REFERENCE:

P8178L-005 pages 46 and 47.

BANK HIGHER K/A:065A2.06: Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is decreasing.

JUSTIFICATION:

a. Incorrect. Plausible as CFCU dampers will lose air supply and cooling capability to the RCP vaults will be reduced; however, not enough to require tripping the RCPs prior to loss of feedwater.

b. Incorrect. Plausible as the charging to regenerative heat exchanger control valve will fail close resulting in a loss of charging. This by itself would result in lowering pressurizer level; however, letdown orifice valves also fail close, resulting in a loss of letdown. The loss of letdown causes pressurizer level to rise. This overcomes the loss of charging because seal injection to the RCPs is still established. Therefore, net effect is that pressurizer level will rise. It will take several hours with no operator actions until a reactor trip would be required in this situation.

c. Incorrect. Plausible as the pressurizer spray valves will fail close. However, normal pressure can be maintained by cycling pressurizer heaters. Also plausible because the PORVs are affected by the loss of instrument air, but will not result in the need to trip the reactor.

d. Correct. The main feedwater regulating and bypass valves will fail close within minutes on a loss of instrument air. This causes steam generator levels to rapidly lower and requiring a reactor trip.

Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 7

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 015 A LOCA outside containment has occurred on Unit 1.

The crew is performing 1E-0, Reactor Trip or Safety Injection.

The crew will transition to 1ECA-1.2, LOCA Outside Containment, due to abnormally high readings on...

a. 1R-09, U1 RC LTDN LINE R

b. 1R-51, U1 MS A STM LINE RAD

c. 1R-26, U1 RHR 11/21 CUBICLE AIR R

d. 1R-15, U1 CDSR AIR EJECT GAS RAD ANSWER C

REFERENCE:

1E-0, page 10 NEW MEMORY K/A:E04 2.1.23: Ability to perform specific system and integrated plant procedures during all modes of plant operation.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that 1R-09 indicates a LOCA from CVCS outside of containment and that 1ECA-1.2 mitigates such a LOCA.

b. Incorrect. Plausible if examinee incorrectly believes that most likely LOCA outside of containment is into the main steam system.

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes that RCS water/steam in the air ejector constitutes a LOCA outside of containment.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 obj 20

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 016 The purpose of 1ECA-1.1, Loss of Emergency Coolant Recirculation, is to:

1) continue attempts to restore emergency coolant recirculation capability,

2) delay depletion of RWST by adding makeup fluid and reducing outflow, and

3) _______________.

a. depressurize the RCS to minimize break flow

b. restore power to a safeguards bus

c. terminate the offsite release

d. diagnose the break location ANSWER A

REFERENCE:

1ECA-1.1, pg 2 NEW MEMORY K/A:E11K1.2: Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).

JUSTIFICATION:

a. Correct.

b. Incorrect. Plausible if the examinee incorrectly believes that the secondary system is a viable heat sink option in this situation.

c. Incorrect. Plausible as this is covered under 1ECA-1.3.

d. Incorrect. Plausible as this is covered under 1ECA-1.2.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 21

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 017 The crew is establishing RCS bleed and feed per 1FR-H.1, Response to Loss of Secondary Heat Sink.

To verify the feed path, the crew will check pumps are RUNNING.

a. Safety Injection

b. Reactor Coolant

c. Auxiliary Feedwater

d. Residual Heat Removal ANSWER A

REFERENCE:

1FR-H.1 pg. 10 NEW MEMORY K/A:E05K2.2: Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

JUSTIFICATION:

a. Correct.

b. Incorrect. Plausible if examinee believes that RCPs are used to circulate water during feed and bleed.

c. Incorrect. Plausible if examinee believes that the immediate outcome of feed and bleed is restoration of the secondary heat sink.

d. Incorrect. Plausible if examinee believes that RHR will be used since it can be used to remove decay heat.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 22

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 018 Transmission System Operations (TSO) has notified the Control Room System Condition RED exists and the system is experiencing major loss of load.

The crew has entered C20.3 AOP12, Grid Voltage or Frequency Disturbances.

To ensure power to (1) is not lost, the crew will start the (2) diesel generator(s).

a. TSC ventilation; (2) D1, D2, D5, and D6

b. the security systems; (2) emergency guardhouse

c. buses 31, 32, 41, and 42; (2) D1, D2, D5, and D6

d. buses 15, 16, 25, and 26; (2) emergency guardhouse ANSWER B

REFERENCE:

C20.3 AOP12 pg 5 NEW MEMORY K/A: 077K3.02: Knowledge of the reasons for the following responses as they apply to Generator Voltage and Electric Grid Disturbances: Actions contained in abnormal operating procedure for voltage and grid disturbances.

JUSTIFICATION:

a. Incorrect. Plausible if the examinee believes that D1, D2, D5, and D6 should be started and power TSC ventilation.

b. Correct.

c. Incorrect. Plausible if the examinee believes that D1, D2, D5, and D6 should be started and power buses 31, 32, 41, and 42.

d. Incorrect. Guardhouse diesel should be started; however the purpose is not to provide power to safeguards buses.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-246 Obj. 5

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 019 Unit 1 is at 50% power.

1PT-485, Turbine 1st Stage Pressure, fails HIGH.

The Crew will enter (1).

Control Rods will be (2) control.

a. 1C23 AOP1, Auto Turbine Runback; (2) left in AUTOMATIC

b. 1C23 AOP1, Auto Turbine Runback; (2) placed in MANUAL

c. 1C5 AOP1, Uncontrolled Rod Motion; (2) left in AUTOMATIC

d. 1C5 AOP1, Uncontrolled Rod Motion; (2) placed in MANUAL ANSWER D

REFERENCE:

1C51.2, 1PT-485 - High; 1C5 AOP1, pgs 2-3 NEW HIGHER K/A: 001 2.4.11: Knowledge of abnormal condition procedures.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that 1PT-485 will control turbine 1st stage pressure.

b. Incorrect. Plausible if examinee incorrectly believes that 1PT-485 will control turbine 1st stage pressure and the proper response to turbine runback is to place rods in manual.

c. Incorrect. Plausible if examinee incorrectly believes that megawatts would not be stable.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-223 Obj. 1.5

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 020 Are TS LCO 3.2.3, Axial Flux Difference (AFD) and TS LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR) met?

LCO 3.2.3 LCO 3.2.4 AFD QPTR

a. MET MET

b. MET NOT MET

c. NOT MET MET

d. NOT MET NOT MET ANSWER D

REFERENCE:

T.S. 3.2.4 T.S. 3.2.3 COLR Figure 5 NEW HIGHER K/A: 005K1.02: Knowledge of the operational implications of the following concepts as they apply to Inoperable / Stuck Control Rod: Flux tilt.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that AFD is less restrictive due to power level being less than 100% and that lower radial flux tilt meets QPTR LCO.

b. Incorrect. Plausible if examinee incorrectly believes that AFD is less restrictive due to power level being less than 100%.

c. Incorrect. Plausible if examinee incorrectly believes that lower radial flux tilt meets QPTR

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY LCO.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-002 Obj. 10A

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 021 Unit 1 is at 100% power.

CS-46291, PRZR LEVEL CONTROL CHANNEL SEL, is in the 2-3 (White-Blue) position.

Pressurizer Level indication is as follows:

No operator actions are taken.

What is the status of Letdown and what is the Charging system flow response?

Letdown Charging Pump Speed

a.

isolated rises

b.

isolated lowers

c.

in service rises

d.

in service lowers ANSWER A

REFERENCE:

1C51.3 1L-428 - LOW, pg 1 MODIFIED HIGHER K/A: 028K2.04: Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following: Pumps.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY JUSTIFICATION:

a. Correct.

b. Incorrect. Plausible if examinee believes that blue channel is interlock channel. In that case, pump speed lowers as actual level increases.

c. Incorrect. Plausible if examinee incorrectly believes that current level is below setpoint and is unaware of the control channel (blue) isolates letdown on a low level.

d. Incorrect. Plausible if examinee incorrectly believes that blue channel is not selected as control or interlock channel and level is above program.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-006 Obj. 3E

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 022 A release of 124/126 Waste Gas Decay Tanks is in progress.

47022-0108, ALARM ON RADIATION MONITORING PANELS TRAIN B, is in alarm.

Immediately after the alarm comes in, the Reactor Operator observes the following indications:

Question continued on next page.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY Question continued from previous page.

What is the status of the Waste Gas release and Train B of Auxiliary Building Special Ventilation (ABSV) Exhaust Fan?

Train B ABSV Release Exhaust Fan

a. Occurring Running

b. Occurring Not Running

c. Terminated Running

d. Terminated Not Running ANSWER C

REFERENCE:

B11 pg 14 NEW HIGHER K/A: 060K3.02: Knowledge of the reasons for the following responses as they apply to the Accidental Gaseous Radwaste: Isolation of the auxiliary building ventilation.

JUSTIFICATION:

a. Incorrect. Plausible if student believes that alarm on 1R-30 secures release.

b. Incorrect. Plausible if student believes that alarm on 1/2R-30 actuates train A of ABSV and if student believes that alarm on 1R-30 secures release.

c. Correct.

d. Incorrect. Plausible if student believes that alarm on 1/2R-30 actuates train A of ABSV.

Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-001A Obj. 4E For the 121/122 ABSV Fans, describe the automatic actions including starts, trips, and interlocks and their set points.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 023 No operator actions are taken.

What is the status of MSIVs and Containment Spray?

MSIVs CTMT Spray

a. OPEN ACTUATED

b. OPEN NOT ACTUATED

c. CLOSED ACTUATED

d. CLOSED NOT ACTUATED ANSWER C

REFERENCE:

B18C, pages 16 and 17.

NEW

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY HIGHER K/A: W/E14EA1.2: bility to operate and/or monitor the following as they apply to the (High Containment Pressure): Operating behavior characteristics of the facility.

JUSTIFICATION:

a. Incorrect. Plausible as CS will be actuated and if examinee incorrectly believes MSIV close setpoint is higher than 25 or if not enough channels are above the actual setpoint.

b. Incorrect. Plausible if examinee incorrectly believes the MSIV and CS setpoints are higher than 25 or if not enough channels are above the actual setpoints.

c. Correct. Steamline isolation signal (MSIVs close) on 2 of 3 High-High CTMT Pressure signals (17 psig). CS actuates automatically when CTMT pressure is >23 psig on 1 of 2 channels on 3 sets of 3 transmitters.

d. Incorrect. Plausible as MSIVs will be closed and if examinee incorrectly believes CS actuation setpoint is higher than 25 or if not enough channels are above the actual setpoint.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-006 Obj. 3F

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 024 The crew is performing 1ES-0.2, SI Termination.

Pressurizer level is 4% and lowering.

Condensate Storage Tank level is 90,000 gal.

Containment pressure is 6.1 psig.

11 and 12 Steam Generator pressures are 750 psig and stable.

The crew will enter...

a. 1E-3, Steam Generator Tube Rupture.

b. 1E-2, Faulted Steam Generator Isolation.

c. 1E-1, Loss of Reactor or Secondary Coolant.

d. C28.1 AOP2, Loss of Condensate Supply to Auxiliary Feedwater.

ANSWER C

REFERENCE:

ES-0.2 Information page and pg. 5 NEW HIGHER K/A: E02EA2.1: Ability to determine and interpret the following as they apply to the (SI Termination): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

JUSTIFICATION:

a. Incorrect. Plausible because inventory would lower during a tube rupture.

b. Incorrect. Plausible if SG level were not able to be maintained rather than PZR level.

c. Correct.

d. Incorrect. Plausible if PZR level were normal and CST level were <10K gallons.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-224 Obj. 7

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 025 The crew is performing 1FR-Z.3, Response to High Containment Radiation.

Which instrument(s) below is (are) designated as post-accident instrumentation?

A.

B.

C.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY D.

ANSWER D

REFERENCE:

H3 pg 70 NEW MEMORY K/A: E16 2.4.3: Ability to identify post-accident instrumentation JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes this instrument is only available post-accident because CTMT Pressure NR instruments provide input for safeguards actuation.

b. Incorrect. Plausible if examinee incorrectly believes this instrument is only available post-accident because CTMT Pressure WR instruments provide input for safeguards actuation.

c. Incorrect. Plausible because CTMT humidity and pressure are used for normal conditions and post-accident, but they are not designated as such.

d. Correct. The white "star" specifically designates this recorder instrument as post-accident use.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj 45

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 026. P8140L-233 2

a. The crew is depressurizing the RCS to refill the pressurizer per 1ES-1.1, Post LOCA Cooldown and Depressurization.

b. Both Pressurizer Spray Valve controllers are in AUTO.

The pressurizer spray valves are currently (1).

The RO will turn the manual control knob on 1HC431K, PRZR PRESS MASTER CONTROL, (2) to RAISE pressurizer level faster.

a. OPEN; (2) CLOCKWISE

b. CLOSED; (2) CLOCKWISE

c. OPEN; (2) COUNTERCLOCKWISE

d. CLOSED; (2) COUNTERCLOCKWISE ANSWER B

REFERENCE:

1ES-1.1 pg. 6 NEW HIGHER K/A: E03EA1.1: Ability to operate and/or monitor the following as they apply to the (LOCA Cooldown and Depressurization): Components and functions of control and safety systems,

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

JUSTIFICATION:

a. Incorrect. Plausible if examinee believes that demand represented on the master controller represents open spray valves.

b. Correct.

c. Incorrect. Plausible if examinee believes that demand represented on the master controller represents open spray valves and that counterclockwise operation will open spray valve further.

d. Incorrect. Plausible if examinee believes that counterclockwise operation will open the spray valve.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-233 objective B.7

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 027 The crew is performing 1ES-0.4, Natural Circulation Cooldown with Steam Void in the Vessel.

RCS subcooling is 60°F and lowering.

Pressurizer level is 2% and lowering.

CST level is 110,000 gallons and lowering.

VCT level is 31% and lowering.

Charging flow is 67 gpm.

One 40 gpm letdown orifice is in service.

The crew will...

a. manually start SI pumps per 1E-1, Loss of Reactor or Secondary Coolant.

b. provide manual makeup per C12.5 AOP2, Malfunction of Automatic Makeup.

c. actuate SI and perform immediate actions of 1E-0, Reactor Trip or Safety Injection.

d. switch to alternate AFW supply per C28.1 AOP2, Loss of Condensate Supply to Auxiliary Feedwater Pump Suction.

ANSWER C

REFERENCE:

1ES-0.4 pg. 3 and Information Page NEW HIGHER K/A:E10EA2.1: Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

JUSTIFICATION:

a. Incorrect. Plausible if examinee believes that information page action of 1E-1 applies.

b. Incorrect. Plausible if examinee believes that makeup should be occurring due to VCT trend.

Can also be plausible if student believes that the makup system makes up directly to the RCS.

c. Correct.

d. Incorrect. Plausible if information page conditions for switching aux feed source are met.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-011A Obj. General

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY

28. P8170L-002 153 Based ONLY on the indications above, which RCP(s), if any, can be started?

a. 11 RCP ONLY

b. 12 RCP ONLY

c. BOTH RCPs

d. NEITHER RCP ANSWER A

REFERENCE:

C3 pg 10 NEW MEMORY K/A: 003A4.03: Ability to manually operate and/or monitor in the control room: RCP lube oil and lift pump motor controls.

JUSTIFICATION:

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes that the illuminated amber light indicates the interlock is not met.

c. Incorrect. Plausible if examinee incorrectly believes that the lift pumps must be running to start the RCPs.

d. Incorrect. Plausible if examinee incorrectly believes that the lift pumps can not be running in order to start the RCPs.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-001A Obj. 3H

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 029 The crew is performing an ALTERNATE DILUTION per 1C12.5, Unit 1 Boron Concentration Control.

CS-46300, MAKE UP MODE SELECTOR, is in ALT DILUTE.

CS-46457, BORIC ACID MAKE-UP CONTROL, is placed in START.

Which valve failed to operate?

a. CV-31200

b. CV-31201

c. CV-31199

d. CV-31206 ANSWER A

REFERENCE:

B12A pg. 34

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY NEW HIGHER K/A: 004 2.1.31: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

JUSTIFICATION:

a. Correct

b. Incorrect. Plausible if the examinee incorrectly believed that this valve should be closed as when doing a boration or manual makeup.

c. Incorrect. Plausible if the examinee incorrectly believed that this valve should be closed as when doing a boration.

d. Incorrect. Plausible if the examinee incorrectly believed that this valve should be closed as when doing a boration.

Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-001A Obj. 4A

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 030 Unit 1 is in Mode 5.

11 Charging Pump is RUNNING.

Train A of Residual Heat Removal is IN SERVICE.

11 and 21 Cooling Water Pumps are RUNNING.

121 Instrument Air Compressor is the TRIM compressor.

Bus 15 locks out.

Unit 1 will lose...

a. Charging Pump flow.

b. Residual Heat Removal flow.

c. Cooling Water header pressure.

d. Instrument Air header pressure.

ANSWER B

REFERENCE:

B20.8 pg.13 PE 151-RL pg. 3 NF-40021, B15 pg. 6 NEW HIGHER K/A: 005K2.01: Knowledge of bus power supplies to the following: RHR Pumps JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that 11 charging pump is powered from Bus 15.

b. Correct.

c. Incorrect. Cooling water does contain safeguards pumps. Plausible if examinee incorrectly believes that safeguards cooling water pumps are powered by bus 15.

d. Incorrect. 121 IA compressor is powered from bus 15. Plausible if examinee incorrectly believes the header isolation valves will close on loss of bus 15.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-003 Obj. 3C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 031 A RED path on Core Cooling exists on the Critical Safety Function status tree.

BOTH 11 and 12 Safety Injection pumps CANNOT be started.

11 and 12 Residual Heat Removal pumps are RUNNING.

The next required action is to depressurize both Steam Generators.

The Steam Generators must be depressurized to...

a. prevent pressurized thermal shock of the reactor vessel.

b. prevent SG from becoming a heat source to the RCS.

c. establish conditions for starting RCPs.

d. enable ECCS flow.

ANSWER D

REFERENCE:

1FR-C.1 Bases, pg. 4 BANK MEMORY K/A: 006K3.01: Knowledge of the effect that a loss or malfunction of the ECCS will have on the following: RCS.

EXPLANATION:

Under the conditions given, a malfunction of the ECCS has resulted in an inadequate core cooling condition. Absent of restoring high pressure injection, the RCS must be depressurized to allow for the accumulators and RHR pumps to inject into the RCS. This is accomplished by rapidly depressurizing the SGs at the maximum rate and, therefore, raises ECCS flow.

JUSTIFICATION:

a. Incorrect. PTS is not a concern in an ICC condition. Plausible if the applicant believes this is a priority over establishing some form of core cooling.

b. Incorrect. Though it may be true that the SGs are acting as a heat sink, an ICC condition exists, and the main priority is to restore some type of ECCS flow. Plausible if the applicant fails to prioritize restoration of ECCS flow correctly.

c. Incorrect. Plausible if the applicant believes that all ECCS is lost, and misinterprets RCP starting conditions.

d. Correct. See EXPLANATION above.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 16

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 032 47012-0406, PRZR RELIEF TANK HI TEMP/LVL/PRESS OR LO LVL, is LIT.

Pressurizer Relief Tank (PRT) temperature is HIGH.

ALL other PRT parameters are normal.

Per C47012-0406, how is PRT temperature lowered?

a. Add makeup to the PRT and drain as necessary.

b. Vent the PRT and refill with nitrogen as necessary.

c. Raise cooling water flow to the PRT Heat Exchanger.

d. Recirculate PRT contents through the RCDT Heat Exchanger.

ANSWER A

REFERENCE:

C47012-0406; B4A page 44; B21B page 45.

NEW MEMORY K/A: 007K4.01: Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the following: Quench tank cooling.

JUSTIFICATION:

a. Correct. Per C47012-0406, the operator is required to open makeup valves to fill the PRT with demineralizer water and open the drain valve as necessary to maintain PRT level in the normal band.

b. Incorrect. Plausible because the PRT does have a vent valve and nitrogen can be added; however, this is only performed if PRT pressure is outside the normal band.

c. Incorrect. Plausible if the examinee incorrectly believes the PRT has a heat exchanger.

This is plausible because most components in the plant that require temperature control have there own heat exchanger to maintain temperature.

d. Incorrect. Plausible if the examinee incorrectly believes the RCDT has a heat exchanger.

Also plausible because the PRT is drained to the RCDT. Also plausible because some plants in the industry require this and/or allow this to lower PRT temperature.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj. 4a

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 033 Unit 1 Control Board CC Surge Tank Level is -7".

Unit 2 Control Board CC Surge Tank Level is +3".

CC-27-8, 11 CC SURGE TNK XTIE ISOL, is CLOSED.

2CC-27-8, 21 CC SURGE TNK XTIE ISOL, is CLOSED.

No operator actions are taken.

Figure B14-03, CC Surge Tank Makeup Valve Logic, is provided.

What is the status of the Unit 1 and Unit 2 CC Surge Tank Make-up Valves?

CV-31432 CV-31433 11 CC SURGE TNK M-U CV 21 CC SURGE TNK M-U CV

a.

OPEN OPEN

b.

OPEN CLOSED

c.

CLOSED OPEN

d.

CLOSED CLOSED ANSWER B

REFERENCE:

B14 pages 8 - 10, & 25.

BANK MEMORY K/A: 008A1.04: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including: Surge tank level.

JUSTIFICATION:

a. Incorrect. Plausible as CV-31432 is open and if examinee misreads logic diagram and incorrectly believes CV-31433 is open. However, it is closed because level in 21 CC Surge tank is greater than +2".

b. Correct.

c. Incorrect. Plausible if examinee confuses or mixes up the setpoints between unit 1 and unit

2.

d. Incorrect. Plausible as CV-31433 is closed and if examinee misreads logic diagram and incorrectly believes CV-31432 is closed. However, it is open because level in 11 CC Surge Tank is less than -6".

Proposed references to be provided to applicants during examination: Figure B14-03 Learning Objective: P8172L-002 Obj. 3e.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 034 11 CC pump is in standby.

12 CC discharge pressure is 104 psig.

12 CC flow is 5000 gpm.

12 CC Heat Exchanger outlet temperature is 100°F.

The Reactor Operator will start 11 CC pump due to...

a. LOW flow rate.

b. HIGH flow rate.

c. HIGH temperature.

d. LOW discharge pressure.

ANSWER B

REFERENCE:

1C14 pg. 6-8; C47020-0502 pg 1 NEW MEMORY K/A: 008A4.10: Ability to manually operate and/or monitor in the control room: Conditions that require the operation of two CCW coolers.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly confuses flow rates given with normal flow rates; also a standby pump would be started for low pressure but not low flow

b. Correct. If system flow demand is too high for the given pump configuration, a second pump will be started to prevent runout on the running pump. At Prairie Island, the CC system is designed such that starting the standby CC pump will automatically place a second CC cooler in service.

c. Incorrect. Plausible if examinee incorrectly believes HX outlet temperatures are too high and that starting a second CC pump would alleviate the high temp condition.

d. Incorrect. Plausible if examinee incorrectly believes discharge pressure is too low and starting a second CC pump would be required.

Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-002 Obj. 7

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 035 Unit 2 is at 50%.

RCS Pressure is 2235 psig.

PRZR Pressure Control is in AUTO.

Group D Backup Heaters are ENERGIZED.

Group C Variable Heaters are ENERGIZED.

2HC-431H, B Spray Valve Control, fails to 100% output.

No operator actions are taken.

The reactor will...

a. trip on LOW pressurizer pressure.

b. trip on HIGH pressurizer pressure.

c. NOT trip due to pressurizer heaters stabilizing pressurizer pressure.

d. NOT trip due to PRZR Pressure Master Controller preventing valve movement.

ANSWER A

REFERENCE:

B7, pgs 17-18 NEW HIGHER K/A: 010K6.03: Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: PZR sprays and heaters.

JUSTIFICATION:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes 100% output is fully closed.

c. Incorrect. Plausible if examinee incorrectly believes PRZR heaters can overcome flow from a single spray valve.

d. Incorrect. Plausible if examinee incorrectly believes individual spray valves cannot be operated independently of the master controller.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-005 Obj. 7B

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 036 Unit 1 is in Mode 4.

Pressurizer pressure is 335 psig.

Pressurizer temperature is 432°F.

Pressurizer level is 65%.

(1) Is a bubble drawn in the pressurizer?

(2) What is being used to maintain pressurizer pressure?

Bubble in PRZR Pressure Control

a. YES Letdown PCV

b. YES PRZR Heaters

c. NO Letdown PCV

d. NO PRZR Heaters ANSWER B

REFERENCE:

1C1.2-M4, pgs 21-22 Steam Tables NEW HIGHER K/A: 010K5.01: Knowledge of the operational implications of the following concepts as they apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables.

JUSTIFICATION:

a. Incorrect. Plausible as a bubble is drawn in the pressurizer and if the examinee incorrectly believes the letdown control valve is used to maintain pressurizer pressure with a bubble in the pressurizer.

b. Correct. With pressure at 335 psig and temperature at 432 F, the fluid in the pressurizer is saturated, indicating there is steam and bubble in the pressurizer. Since there is a bubble in the pressurizer, the letdown pressure control valve will have little to no effect on pressurizer pressure. Per 1C1.2-M4, the operator is directed to turn on pressurizer heaters to raise pressurizer pressure and turn off pressurizer heaters to lower pressure.

c. Incorrect. Plausible if the examinee incorrectly converts psig to psia when using the steam tables to determine if the pressurizer fluid is saturated. This could result in the examinee incorrectly believing the fluid in the pressurizer is subcooled. With the pressurizer fluid being subcooled, the letdown pressure control valve is the correct method to use to control pressurizer pressure.

d. Incorrect. Plausible if the examinee incorrectly converts psig to psia when using the steam tables to determine if the pressurizer fluid is saturated. This could result in the examinee incorrectly believing the fluid in the pressurizer is subcooled. Also plausible if the examinee incorrectly believes pressurizer heaters are used to control pressurizer pressure during all modes. Heaters are the normal method pressure control.

Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: P8170L-005 Obj. 3J

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 037 T is 100%.

A Steam Generator PORV lifts.

Rod Control is in MANUAL.

Turbine Control is in FSP Mode.

What is the response of ACTUAL T and the OVER POWER (OPT) SETPOINT?

ACTUAL T OPT SETPOINT

a. RISES NO CHANGE

b. NO CHANGE LOWERS

c. LOWERS NO CHANGE

d. NO CHANGE RISES ANSWER A

REFERENCE:

B8 pgs 5-7 BANK HIGHER K/A: 012A1.01: Ability to predict and/or monitor Changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including: Trip setpoint adjustment.

JUSTIFICATION:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes that Thot and Tcold will both lower by the same amount when a PORV is open and examinee incorrectly believes that the value of K5 is still positive for decreasing Tave.

c. Incorrect. Plausible if examinee incorrectly believes that Tcold is limited by steam generator pressure and will lower less than Thot.

d. Incorrect. Plausible if examinee incorrectly believes that Thot and Tcold will both lower by the same amount when a PORV is open and examinee incorrectly believes that the value of K6 is still positive for Tave less than T'.

Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-004 Obj. 5D

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 038 The crew is in 2E-0, Reactor Trip or Safety Injection.

RCS pressure is 1500 psig and lowering.

Containment pressure is 6 psig and rising.

21 Steam Generator WR level is 55% and stable.

21 Steam Generator pressure is 700 psig and slowly lowering.

22 Steam Generator WR level is 57% and stable.

22 Steam Generator pressure is 675 psig and slowly lowering.

o 2R-15, Unit 2 Condenser Air Ejector Gas Monitor, is reading 5.5 x101 CPM.

Safety Injection has (1) and the crew will transition to (2).

a. (1) ACTUATED; (2) 2E-1, Loss of Reactor or Secondary Coolant

b. (1) NOT ACTUATED; (2) 2E-2, Faulted Steam Generator Isolation

c. (1) (ACTUATED; (2) 2E-3, Steam Generator Tube Rupture

d. (1) NOT ACTUATED: (2) 2ES-0.1, Reactor Trip Recovery ANSWER A

REFERENCE:

2E-1, pg 2; B18C, pg 13 NEW HIGHER K/A: 013A2.01: Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: LOCA.

JUSTIFICATION:

a. Correct. Lowering RCS pressure (<1830# for SI), rising CTMT pressure, slowly lowering SG pressures (cooldown), stable SG levels, and no AE radiation are indicative of a LOCA and 2E-1 is the appropriate response.

b. Incorrect. Plausible if examinee incorrectly believes the lowering SG pressures are indicative of a faulted SG; also if examinee does not know the SI actuation RCS pressure.

In this case, SG pressures are not lowering uncontrollably or are completely depressurized, and both levels are stable.

c. Incorrect. Plausible as SI is actuated and if examinee incorrectly believes a tube rupture is in progress because 22 SG level is higher than 21; however, levels are stable and not rising.

Also, 2R-15 is not in alarm.

d. Incorrect. Plausible if examinee incorrectly believes the indications are normal after a reactor trip.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-006 Obj. 5B

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 039 Unit 1 is at 100% power.

Bus 14 locks out.

What is the status of CFCUs?

11 & 13 12 & 14 CFCUs CFCUs

a. RUNNING RUNNING

b. RUNNING NOT RUNNING

c. NOT RUNNING RUNNING

d. NOT RUNNING NOT RUNNING ANSWER A

REFERENCE:

B19 pg 16, ERCS screenshots EA15, EA16, EA25, EA26 NEW MEMORY K/A: 022K2.01: Knowledge of power supplies to the following: Containment cooling fans.

JUSTIFICATION:

a. Correct. 11 & 13 CFCUs are powered from Bus 15 and 12 & 14 CFCUs are powered from Bus 16; therefore, all four CFCUs will remain running.

b. Incorrect. Plausible if examinee incorrectly believes 12 & 14 CFCUs are powered from Bus

14. This is plausible because bus 14 is an even number and 12 & 14 CFCUs are even numbers.

c. Incorrect. Plausible if examinee incorrectly believes 11 & 13 CFCUs are powered from Bus

14. This is plausible because Prairie Island has some odd number components powered from even number buses. For example, 13 Condensate Pump is powered from bus 14, 23 Condensate Pump is powered from Bus 24. Also, 11 and 13 Charging Pumps are powered from bus 16 and 12 Charging Pump is powered from bus 15.

d. Incorrect. Plausible if examinee incorrectly believes CFCU (480v) MCCs are both powered from Bus 14. This is plausible because some power supplies come from one source. For example, control power for RCPs are from one train; all rod bottom lights get power from one safeguards bus; all rod position indications get power from one safeguards bus too.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009H Obj. 3A

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 040 A Safety Injection has occurred on Unit 1.

Did the Cooling Water and Chilled Water supply and return valves operate as expected?

Cooling Water Valves Chilled Water Valves

a. YES YES

b. YES NO

c. NO YES

d. NO NO ANSWER C

REFERENCE:

1E-0 Attachment L, pg. 7 NEW

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY HIGHER K/A: 022A3.01: Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation.

JUSTIFICATION:

a. Incorrect. Plausible if the cooling water valves were open.

b. Incorrect. Plausible if all valve positions were changed.

c. Correct.

d. Incorrect. Plausible if the chilled water valves were open.

Proposed references to be provided to applicants during examination: None Learning Objective: P8176L-003 Obj. 4.C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 041. P8180L-002 43 Containment pressure is 26 psig.

Containment spray has actuated.

What action will the Reactor Operator take?

a. Reset Containment Spray

b. Manually start 11 Containment Spray Pump

c. Place 11 Containment Spray Pump in PULLOUT

d. Place 12 Containment Spray Pump in PULLOUT ANSWER B

REFERENCE:

1E-0 Attachment L pg 4 NEW

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY HIGHER K/A: 026A4.01: Ability to manually operate and/or monitor in the control room: CSS controls.

JUSTIFICATION:

a. Incorrect. Plausible if manual start of 11 containment spray pump had already been attempted.

b. Correct.

c. Incorrect. Plausible if MV-32103 failed to open.

d. Incorrect. Plausible if MV-32105 failed to open.

Proposed references to be provided to applicants during examination: 1E-0 Attachment L, pg 4 Learning Objective: P8180L-002 Obj. 4B

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 042 CV-31060, 22 AFWP TURB TRIP/THROTTLE VLV, is OPEN and RESET.

Main Steam to 22 Turbine Driven Auxiliary Feedwater pump is (1) and RCS Tavg is being controlled by the (2).

a. (1) AVAILABLE; (2) Steam Dump System

b. (1) AVAILABLE; (2) Steam Generator PORV(s)

c. (1) NOT AVAILABLE; (2) Steam Dump System

d. (1) NOT AVAILABLE; (2) Steam Generator PORV(s)

ANSWER B

REFERENCE:

B27, pgs 3 - 7 NEW HIGHER K/A: 039 2.1.19: Ability to use plant computers to evaluate system or component status.

JUSTIFICATION:

a. Incorrect. Plausible as MS is available to 22 TDAFWP and if examinee incorrectly believes SD can be used with MSIVs closed; however, in this case SG PORVs are being used.

b. Correct. MSIVs are closed; therefore, SD cannot be used despite two atmospheric valves indicating open. This is a typical lineup for U2 in M3. MVs 32019 and 32020 are the steam supplies to 22 TDAFWP. Only one is required to be open to supply the pump.

c. Incorrect. Plausible if examinee incorrectly believes SD can be used with MSIVs closed and that both MVs must be open to supply the pump.

d. Incorrect. Plausible as SG PORVs are being used and if examinee incorrectly believes that

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY both MVs must be open to supply the pump.

Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-001 Obj. 3I

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 043 Unit 1 is at 100% power.

BOTH Main Feed Regulating Valves are in MANUAL.

11 Steam Generator narrow range level is 36% and stable.

12 Steam Generator narrow range level is 44% and stable.

The Reactor Operator will throttle (1) on the (2) Main Feed Regulating Valve.

a. (1) OPEN; (2) A

b. (1) OPEN; (2) B

c. (1) CLOSED; (2) A

d. (1) CLOSED; (2) B ANSWER A

REFERENCE:

1C28.2 page 34 NEW HIGHER K/A: 059K1.03: Knowledge of the physical connections and/or cause effect relationships between the MFW and the following systems: S/GS.

JUSTIFICATION:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes 11 SG level is controlled by B MFRV; also if examinee incorrectly believes 12 SG level is too high and opening the MFRV will cause level to lower.

c. Incorrect. Plausible if examinee incorrectly believes 12 SG is controlled by A MFRV and closing the MFRV will raise level in 11 SG.

d. Incorrect. Plausible if examinee incorrectly believes 12 SG level is above program Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-003 Obj. 3.J.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 044 Unit 1 is at 100% power.

11 Turbine Driven Auxiliary Feedwater Pump (TDAFWP) is Out of Service.

Reactor and turbine automatically trip.

Which valve will the crew throttle to prevent overfilling 11 Steam Generator?

a. CV-31127, A MAIN FW

b. CV-31364, A BYPASS FW

c. MV-32323, 11 FWP DISCH VLV

d. MV-32381, 12 MD AFWP to 11 STM GEN ANSWER D

REFERENCE:

1ES-0.1 Background Information pg. 2 NEW MEMORY K/A: 059A2.03: Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Overfeeding event.

JUSTIFICATION:

a. Incorrect. Plausible if the examinee incorrectly believes that MFRV does not isolate on Hi-Hi SG level.

b. Incorrect. Plausible if the examinee incorrectly believes that MFRBV does not isolate on Hi-Hi SG level.

c. Incorrect. Plausible if the examinee incorrectly believes that MF discharge valve must be closed to isolate MF from SG.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-011 Obj. Gen

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 045 A Loss of Heat Sink has occurred on Unit 1.

11 TD AFW Pump is out of service.

Bus 16 is locked out.

1R Transformer is locked out.

The crew will restore feed to the Unit 1 Steam Generators using...

a. 12 MD AFW Pump.

b. 21 MD AFW Pump.

c. 11 Main Feed Pump.

d. 12 Main Feed Pump.

ANSWER B

REFERENCE:

B20.5 pgs 21 and 22; B28A pg 9 B28B pg. 5 NEW HIGHER K/A: 061K2.02: Knowledge of bus power supplies to the following: AFW electric drive pumps.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes 12 MD AFW Pump is powered by Bus 15 instead of Bus 16. However, 12 MD AFW Pump is powered from Bus 16. This is plausible because Unit 2 21 MD AFW Pump is powered from Bus 25.

b. Correct. Since a loss of heat sink is occurring, both SGs are well below 13% (loss of heat sink occurs when both SGs are below 50% WR and less than 200 gpm AFW flow) and a automatic reactor trip has occurred. When the reactor trips, a loss of the 1M transformer occurs. Since the 1R and 1M transformers are lost, there is no power available to buses 11 and 12. Bus 11 provides power to 11 Main Feed Pump and Bus 12 provides power to 12 Main Feed Pump. Therefore, 11 and 12 Main Feed Pumps are NOT available. Since Bus 16 is locked out, 12 MD AFW Pump is also NOT available. 21 MD AFW Pump receives power from Bus 25, which is still available because Bus 25 receives power from the 2RY transformer. The 2RY transformer is not impacted from the loss of 1R transformer. The 21 MD AFW Pump can provide auxiliary feedwater flow to the Unit 1 Steam Generators via a cross connect valve.

c. Incorrect. Plausible if examinee incorrectly believes the 11 Main Feed Pump still has power available. This is plausible if examinee believes power to the Main Feed Pump is provided by a bus other than bus 11 such as Bus 13 or Bus 15. Also plausible if examinee does not understand that a loss of 1R Transformer results in a loss of Bus 11 and Bus 12. Also plausible if examinee does not understand that the reactor would already be tripped during a loss of heat sink and this results in a loss of the 1M transformer.

d. Incorrect. Plausible if examinee incorrectly believes the 12 Main Feed Pump still has power available. This is plausible if examinee believes power to the Main Feed Pump is provided by a bus other than bus 12 such as Bus 14 or Bus 15. Also plausible if examinee does not understand that a loss of 1R Transformer results in a loss of Bus 11 and Bus 12. Also plausible if examinee does not understand that the reactor would already be tripped during a

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY loss of heat sink and this results in a loss of the 1M transformer.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007 Obj. 3C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 046 11 Turbine Driven Auxiliary Feedwater pump (TD AFWP) is RUNNING.

MV-32238, 11 TD AFWP TO 11 STM GEN, is OPEN.

MV-32239, 11 TD AFWP TO 12 STM GEN, is OPEN.

The Reactor Operator CLOSES MV-32238.

What is the effect on 11 TD AFW pump discharge pressure and 11 SG AFW flow?

11 TD AFWP AFW FLOW PRESSURE to 11 SG

a. RISE RISE

b. RISE LOWER

c. LOWER RISE

d. LOWER LOWER ANSWER B

REFERENCE:

1E-0 pg 6; 1C28.1 pg 6, B28B pg 17 NEW MEMORY JUSTIFICATION:

K/A: 061K5.03: Knowledge of the operational implications of the following concepts as they apply to the AFW: Pump head effects when control valve is shut.

a. Incorrect. Plausible as 11 TDAFW pump pressure will rise and if examinee incorrectly believes that flow will also rise.

b. Correct. TDAFWP discharge pressure rises due to higher pump head effects from closing discharge valve. Flow to 11 SG will lower but flow to 12 SG will rise as the total AFW flow is not changing, but rather where flow is being directed.

c. Incorrect. Plausible if examinee incorrectly confuses pressure and flow effects on the pump and to which SG flow is being directed.

d. Incorrect. Plausible as AFW flow lowers to 11 SG and if examinee incorrectly believes closing a discharge valve will lower system pressure.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007 Obj. 5 State the functional interrelationship between the Auxiliary Feedwater System and Steam Generators.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 047 Unit 2 is at 100%.

2RS Transformer is Out of Service.

Bus 25 is powered from 1RY source.

Breaker 6H2, 10 BANK XFMR to 161KV BUS 1, locks out.

No operator actions are taken.

C92000-PT79 is provided.

What is supplying power to Bus 25 and Bus 26?

a. 1RY

b. CT12

c. D1 and D2

d. D5 and D6 ANSWER D

REFERENCE:

B20.5 pg 10; C92000-PT79 NEW HIGHER K/A: 062K3.02: Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: ED/G.

JUSTIFICATION:

a. Incorrect. Plausible if student incorrectly believes that 1R is available with 6H2 lockout.

b. Incorrect. Plausible if student incorrectly believes that CT12 is available with 6H2 lockout.

c. Incorrect. Plausible is student incorrectly believes that Unit 1 and Unit 2 safeguards busses have been cross tied.

d. Correct.

Proposed references to be provided to applicants during examination: C92000-PT79 Learning Objective: P8186L-008 Obj. 4C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 048 Based on the picture above, control power for 11 and 12 RCP is provided by Battery Charger.

a. 11

b. 12

c. 21

d. 22 ANSWER C

REFERENCE:

1C20.9 AOP1 pg 4 NEW HIGHER K/A: 063K4.01: Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Manual/automatic transfers of control.

JUSTIFICATION:

a. Incorrect. Plausible if student incorrectly believes that Bus 111 voltage indicates that 11 and 12 RCPs are being powered from the normal source.

b. Incorrect. Plausible if student incorrectly believes that U! RCP control power automatically switches to U1 B train on loss of power to Panel 11.

c. Correct.

d. Incorrect. Plausible if student incorrectly believes that control power for RCPs switches units and trains on loss of power to panel 11 to avoid single point vulnerability for all station RCP control power.

Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-005 Obj. 4B

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 049 Unit 2 is at 100% power.

The D6 Emergency Diesel Generator 1B Starting Air Receiver relief valve has failed OPEN.

The D6 Emergency Diesel Generator 1B Starting Air Receiver has been isolated.

A loss of OFFSITE power occurs on Unit 2.

D6 Emergency Diesel Generator will...

a. NOT start.

b. Start and run on BOTH engines.

c. Start and run on Engine 1 ONLY.

d. Start and run on Engine 2 ONLY.

ANSWER B

REFERENCE:

2C20.7, pg 7 B38C, pg 62 BANK FUNDAMENTAL K/A: 064K6.07: Knowledge of the effect that a loss or malfunction of the air receivers will have on the following: ED/G.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes both starting air systems are needed to start both engines on D6 or that D6 will not start on loss of offsite power.

b. Correct. Each engine (1 & 2) has two air receivers (1A/1B & 2A/2B) feeding air distributors on respective sides of each engine, so both engines will receive starting air. Only one air receiver is needed to start an engine. D6 will start due to safeguard bus loss of voltage.

c. Incorrect. Plausible if examinee incorrectly believes two starting air receivers are needed to start each engine on D6.

d. Incorrect. Plausible if examinee incorrectly believes two starting air receivers are needed to start each engine on D6 and that 1B air receiver supplies engine 2.

(Note: "Start" means the air system operates to turn over the diesel, "run" means fuel is supplied to the cylinder to rotate the generator)

Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-014 Obj. 7B.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 050 The automatic actions of a 2R-19, STEAM GENERATOR BLOWDOWN LIQUID MONITOR, alarm will isolate the 21 Steam Generator Blowdown Flash Tank from...

a. the atmosphere.

b. the Discharge Canal.

c. 11 Steam Generator Blowdown Flash Tank.

d. the Steam Generator Blowdown Hold Up Tanks.

ANSWER B

REFERENCE:

C47047 2R-19 NEW MEMORY K/A: 073K4.01: Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint.

JUSTIFICATION:

a. Incorrect. Plausible if the examinee incorrectly believes the function of 2R-19 is similar to 2R-39 (isolates CC surge tank vent).

b. Correct. 2R-19 automatic actions for 2R-19 are to isolate flow from U2 SGs to 21 Flash Tank and from 21 Flash Tank to the river.

c. Incorrect. Plausible if the examinee incorrectly believes the 11 and 21 Flash Tanks are cross connected, similar to the SGBD HUTs.

d. Incorrect. Plausible if the examinee incorrectly believes discharge to the river uses administrative controls specified in the ODCM because automatic isolation does not occur.

Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-002 Obj.3F

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 051 D2 Diesel Generator is RUNNING.

No operator actions are taken.

D2 Diesel Generator will...

a. trip on high exhaust temperature.

b. trip on high jacket coolant temperature.

c. NOT trip, because D2 is NOT cooled by the Cooling Water System.

d. NOT trip, because the Cooling Water System parameters are satisfactory.

ANSWER B

REFERENCE:

C55300-0301 NEW HIGHER K/A: 076A1.02: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

JUSTIFICATION:

a. Incorrect. Plausible as exhaust temperature will increase based on CL flow shown; however, no such trip exists.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly believes that D2 is not cooled by cooling water similar to D5 and D6.

d. Incorrect. Plausible if examinee incorrectly believes that the high CL flow rate will provide sufficient cooling or if the examinee incorrectly believes that D2 is cooled by Loop A.

Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-004 Obj. 3.1.E

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 052 Both Units are at 100% power.

11 and 21 Motor Driven CL pumps are running.

A Safety Injection occurs on Unit 2.

The 121 Motor Driven Cooling Water Pump is...

a. aligned to both units.

b. isolated from both units.

c. aligned to Loop A cooling water.

d. aligned to Loop B cooling water.

ANSWER D

REFERENCE:

B35 pg 19 BANK MEMORY K/A: 076 2.2.3: Knowledge of the design, procedural, and operational differences between units.

JUSTIFICATION:

a. Incorrect. Plausible as this is the normal lineup for 121 Motor Driven Cooling Water Pump; but not in this case.

b. Incorrect. Plausible as this would be the lineup if a SI occurred on both units.

c. Incorrect. Plausible as this would be the lineup if only a Unit 1 SI occurred; however, an SI occurred on Unit 2.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8176L-003 Obj. 5.A.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 053 121 and 123 Air Compressors are RUNNING.

121 Air Receiver pressure lowers from 100 psig to 65 psig.

123 Air Receiver pressure lowers from 100 psig to 90 psig.

No operator actions are taken.

Based ONLY on the indications above, what is the status of the following valves?

MV-32314 MV-32315 INST AIR HEADER INST AIR HEADER ISOLATION VALVE A ISOLATION VALVE B

a. OPEN OPEN

b. OPEN CLOSED

c. CLOSED OPEN

d. CLOSED CLOSED ANSWER C

REFERENCE:

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY B34 pages 15, 16, and 19 NEW MEMORY K/A: 078A3.01: Instrument Air System (IAS): Ability to monitor automatic operation of the IAS, including: Air pressure.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that set point for valve closure is less than 65 psig.

b. Incorrect. Plausible if examinee incorrectly believes that valves are normally closed and open on low header pressure.

c. Correct. Isolation valve A closes on low pressure (<80 psig) in 121 air receiver with 121 compressor running. Isolation valve B closes on low pressure in 123 receiver with 123 compressor running.

d. Incorrect. Plausible if examinee believes that the set point for valve closure is greater than 90 psig.

Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 3E

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 054 Unit 1 Shield Building ventilation has auto started.

Shield Building fans and dampers are aligned per attached picture.

Train (1) Shield Building Recirc Damper has failed to reposition (2).

a. (1) A; (2) OPEN

b. (1) A; (2) CLOSE

c. (1) B ; (2) OPEN

d. (1) B; (2) CLOSE ANSWER A

REFERENCE:

B19, pgs 25-27 BANK HIGHER K/A: 103K1.03: Containment System: Knowledge of the physical connections and/or cause effect relationships between the containment system and the following systems: Shield Building

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY Vent system.

JUSTIFICATION:

a. Correct. Recirc damper opens at 2"

b. Incorrect. Plausible if it is believed the set point for recirc damper closure has been met.

c. Incorrect. Plausible if it is believed the set point for recirc damper closure has NOT been met.

d. Incorrect. Plausible if it is believed the set point for recirc damper opening has NOT been met.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009C Obj. 5C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 055 INITIALLY:

Containment Isolation occurred.

11 and 12 Containment Vacuum Breakers operated as expected.

NOW:

Containment to Annulus D/P is as follows:

44104-A7, 11 CONTMT VAC BKR CLOSED, is NOT LIT.

44104-B7, 12 CONTMT VAC BKR CLOSED, is LIT.

What is the status of 11 and 12 Containment Vacuum Breakers?

11 CNTMT VAC BKR 12 CNTMT VAC BKR

a. Failed to CLOSE Failed to OPEN

b. Failed to CLOSE CLOSED as expected

c. OPENED as expected Failed to OPEN

d. OPENED as expected CLOSED as expected ANSWER C

REFERENCE:

B19 pgs. 8-9 BANK HIGHER K/A: 103A3.01: Containment: Ability to monitor automatic operation of the containment system, including: Containment isolation JUSTIFICATION:

a. Incorrect. Plausible as 12 Vac Bkr failed to open; however, 11 Vac Bkr opened as expected.

b. Incorrect. Plausible if examinee does not know the correct setpoint and proper operation of the vacuum breakers.

c. Correct. Since DP is greater than negative.4, then both vacuum breakers will normally open.

d. Incorrect. Plausible as 11 Vac Bkr opened as expected; however, 12 Vac Bkr failed to

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY open.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009F Obj. 7B

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 056 Unit 1 is at 100% power.

A pressurizer SAFETY valve fails OPEN, causing a pressurizer vapor space accident.

1) Is this leak isolable from the control room?

2) After 20 minutes, what will LEVEL be in the pressurizer?

ISOLABLE LEVEL

a. NO 100%

b. NO 0%

c. YES 100%

d. YES 0%

ANSWER A

REFERENCE:

1E-1, page 2 1C4 AOP1 page 4 NEW HIGHER K/A:002K6.12: Reactor Coolant System (RCS): Knowledge of the effect or a loss or malfunction on the following RCS components: Code Safety valves.

JUSTIFICATION:

a. Correct. Initially, pressurizer level decreases for approximately the first 45 seconds after the initiating event, causing a reactor trip and safety injection. The PRT rupture disc fails and inventory is lost to containment. As the bubble transfers to the core, level refills to 100%.

There are no isolation valves either in the outplant or in control room that can be operated to prevent this outcome.

b. Incorrect. Plausible if examinee mistakenly believes that the loss of inventory will cause PRZR LVL to go down.

c. Incorrect. Plausible because level will refill to 100% if examinee confuses safety with PORV.

d. Incorrect. Plausible if examinee confuses a safety valve with a PORV and incorrectly believes that the loss of inventory will drain the pressurizer prior to the valve being isolated.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj 3.J.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 057 Unit 1 is at 100% power.

Tavg is 560°F.

All RPIs are reading 0 steps.

Reactor trip breakers are CLOSED.

NO Rod at Bottom lights are lit.

The following annunciators are in alarm:

47013-0207, CONTROL BANKS LO-LO LIMIT.

47013-0307, CONTROL BANKS LO LIMIT.

47013-0407, ROD AT BOTTOM.

47013-0607, ROD POSITION POWER SUPPLY FAILURE.

The Reactor Operator is required to...

a. trip the reactor per 1C5 AOP4, Dropped RCCA.

b. borate the RCS per 1C12.5, Unit 1 Boron Concentration Control.

c. repower RPIs from Unit 2 per C47013-0607, Rod Position Power Supply Failure.

d. manually insert control rods per 1FR-S.1, Response to Nuclear Power Generation/ATWS.

ANSWER C

REFERENCE:

C47013-0607 NEW HIGHER K/A:014A2.02: Rod Position Indication System (RPIS): Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of power to the RPIS.

JUSTIFICATION:

a. Incorrect. Plausible as the reactor has not tripped and this would be the correct action if examinee incorrectly believes that a dropped rod has occurred based on 47013-0407 being in alarm.

b. Incorrect. Plausible if examinee incorrectly believes, based on 47013-0207/0307 that control rods have automatically inserted to the lo-lo limit. Borating would cause rods to withdraw above the rod insertion limits and restore SDM.

c. Correct.

d. Incorrect. Plausible if the examinee incorrectly believes that the alarms that are in indicate the reactor should have tripped. The indications given indicated the reactor has not tripped. If the reactor cannot be tripped and an ATWS is occurring, then manually inserting rods is correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-005 Obj. 3.D

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 058 The Train A Inadequate Core Cooling Monitor control room plasma display is unavailable.

(1) Where can Train A Core Exit Thermocouples be monitored?

(2) What thumbwheel position will display a Core Exit Thermocouple temperature?

Thumbwheel Location Position

a. Hot Shutdown Panel 08

b. Hot Shutdown Panel 30

c. Event Monitoring Room 08

d. Event Monitoring Room 30 ANSWER D

REFERENCE:

B10 pg 15 NEW MEMORY K/A:017A3.02: In-Core Temperature Monitor System (ITM): Ability to monitor automatic operation of the ITM system including: Measurement of in-core thermocouple temperatures at panel outside control room.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY JUSTIFICATION:

a. Incorrect. Plausible if student believes that local panel is near HSP and CETC are RTDs.

b. Incorrect. Plausible if student believes that local panel is near HSP.

c. Incorrect. Plausible if student believes that CETC are RTD's.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-001A Obj. 3.11.G.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 059 Unit 1 is in MODE 6.

Unit 2 is in MODE 1.

A Containment Purge is in progress on Unit __(1)__ with a flowrate of __(2)__ cfm.

a. (1); (2) 4,000

b. (1); (2) 33,000

c. (2); (2) 4,000

d. (2); (2) 33,000 ANSWER B

REFERENCE:

1C19.2, page 8 P8180L-009E pg. 7 NEW HIGHER

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY K/A:029A4.01: Containment Purge System: Ability to manually operate and/or monitor in the control room: Containment purge flow rate.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that a containment in-service purge (little) is occurring.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly believes that a containment in-service purge (little) is occurring and that in-service purge is conducted on the operating unit.

d. Incorrect. Plausible if examinee incorrectly believes that purges are performed on an operating unit.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009E Obj. 4A

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 060 Unit 2 was tripped on April 11 at 0100.

Unit 2 entered Mode 6 on April 13 at 0300.

The crew is performing D5.2, Reactor Refueling Operations.

A full Unit 2 core offload to 122 Spent Fuel Pool is complete.

A loss of SFP cooling occurs on April 23 at 1300.

Figure C1-34, TIME TO BOILING IN THE SPENT FUEL POOL, is provided.

Time to boil is hours.

a. 8

b. 12

c. 18

d. 34 ANSWER B

REFERENCE:

Figure C1-34 NEW HIGHER K/A:033 2.1.25: Spent Fuel Cooling System: Ability to interpret reference materials, such as graphs, curves, tables, etc.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly uses time from entering Mode 6 (250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />) on Fig. C1-34 and Abnormal Case.

b. Correct. The time to SFP boiling is dependent upon the number of discharged fuel assemblies and the time following reactor trip. A full core heat load stored in the SFP is a Full Normal Case. The time since reactor trip is 12 days and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />). Using Fig C1-34, Full Normal Case, the minimum time to boil comes out to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. Incorrect. Plausible if examinee correctly uses time after trip (300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />) but incorrectly uses Normal Case on Fig. C1-34.

d. Incorrect. Plausible if examinee incorrectly uses time after trip to Mode 6.

Proposed references to be provided to applicants during examination: Fig. C1-34 Learning Objective: P8182L-004 Obj. 7B

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 061 Fuel is being removed from the reactor core.

Status of Incore Flux Thimbles Sump C Access

a. INSTALLED ALLOWED

b. INSTALLED NOT ALLOWED

c. REMOVED ALLOWED

d. REMOVED NOT ALLOWED ANSWER D

REFERENCE:

D67, page 4 (purpose); page 5 (Precaution 3.2)

NEW MEMORY K/A:034K1.04: Fuel Handling Equipment System: Knowledge of the physical connections and/or cause effect relationships between the Fuel Handling System and the following systems:

NIS.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes incore flux detectors remain in the core during refueling in order to meet TS LCO 3.9.3 for 2 SR instruments operable during refueling.

Sump C access is allowed when flux thimbles and incore flux monitors are installed.

b. Incorrect. Plausible as Sump C access is not allowed because incore flux thimbles are required to be removed and if examinee incorrectly believes incore flux detectors remain in the core during refueling in order to meet TS LCO 3.9.3 for 2 SR instruments operable during refueling.

c. Incorrect. Plausible as incore flux thimble are removed and if examinee incorrectly believes Sump C access is allowed with flux monitors and thimbles removed.

d. Correct. Per D67, Purpose and Precaution 3.2.

Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-001 Obj. 6

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 062 Unit 1 is at 100% power.

A Safety Injection occurs on Unit 1.

Unit 1 Air Ejector exhaust is aligned to Ventilation.

a. Turbine Building

b. Rad Waste Building

c. Auxiliary Building Normal

d. Auxiliary Building Special ANSWER D

REFERENCE:

B19 pg 29; B26 pg. 3 NEW MEMORY K/A:055A3.03: Condenser Air Removal System (CARS): Ability to monitor automatic operation of the CARS, including: Automatic diversion of CARS exhaust.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that the air ejector exhausts from the building in which the air ejector is physically located.

b. Incorrect. Plausible if the examinee incorrectly believes that is desirable to have air ejectors aligned to rad waste in the event of a tube rupture.

c. Incorrect. Plausible if examinee confuses the alignment during normal and emergency conditions.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-001 Obj. 3F

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 063 The Reactor Coolant Drain Tank is NORMALLY aligned for discharge to the...

a. Aerated Sump Tank.

b. CVCS Holdup Tanks.

c. Chemical Drain Tank.

d. Miscellaneous Drains Tank.

ANSWER B

REFERENCE:

C21.1.3.3, pgs. 8 & 10 NEW MEMORY K/A:068K1.07: Liquid Radwaste System: Knowledge of the physical connections and/or cause effect relationships between the Liquid Radwaste System and the following: Sources of liquid wastes for LRS.

JUSTIFICATION:

a. Incorrect. Plausible if examinee confuses the drain lineup for the RCDT with RHR Pit sumps.

b. Correct. The RCDT can be aligned to CVCS HUTs (normal), RWST, or WHUT. These are NARTD systems which cannot be vented without processing.

c. Incorrect. Plausible if examinee incorrectly believes all chemicals must be processed through the chem drain tank. The RCDT does contain chemicals such as lithium and peroxide.

d. Incorrect. Plausible if examinee incorrectly believes misc drains collection tank processes radioactive sludge which is concentrated for off-site burial.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 064 121 Control Room Chiller is RUNNING.

R-24, CONTROL ROOM AIR SUPPLY MONITOR B, is in alarm.

R-24 is reading offscale HIGH.

No operator actions are taken.

What is the status of the Control Room Cleanup Fans?

121 CR 122 CR Cleanup Fan Cleanup Fan

a. RUNNING RUNNING

b. RUNNING NOT RUNNING

c. NOT RUNNING RUNNING

d. NOT RUNNING NOT RUNNING ANSWER C

REFERENCE:

B11, page 37 47048 R-24 MODIFIED HIGHER K/A:072K4.03: Area Radiation Monitoring System (ARM): Knowledge of ARM system design feature(s) and/or interlock(s) which provide for the following: Plant ventilation systems.

JUSTIFICATION:

a. Incorrect. Plausible as 122 fan will be running, and if examinee incorrectly believes either train will start both 121 and 122 fans; however, in this case the fans are train specific whereas both air supply dampers are actuated by either train.

b. Incorrect. Plausible if examinee incorrectly believes the same train cleanup fan starts with the already running chiller; however, in this case the cleanup fan train that starts coincides with the same train ARM.

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes that BOTH trains of ARMs (R-23/R-24) must be in alarm in order to start the CR cleanup fans.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009I Obj. 3E

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 065 MV-32318, SERVICE AIR HDR ISOL VLV, will automatically (1) if (2) Air pressure lowers below 85 psig.

a. (1) OPEN; (2) Instrument

b. (1) OPEN; (2) Station

c. (1) CLOSE; (2) Instrument

d. (1) CLOSE; (2) Station ANSWER C

REFERENCE:

B34 page 17.

NEW MEMORY K/A:079K4.01: Station Air System (SAS): Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with IAS.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes MV-32318 serves as a method to automatically supplement the Instrument Air System from the Station Air System. MV-32318 does NOT have a auto open feature.

b. Incorrect. Plausible if examinee incorrectly believes MV-32318 serves a method to automatically supplement the Station Air System from the Instrument Air System. MV-32318 does NOT have a auto open feature.

c. Correct.

d. Incorrect. Plausible as MV-32318 does automatically close on low pressure; however, it closes on low pressure in the Instrument Air System, NOT the Station Air System. This is plausible if the examinee incorrectly believes MV-32318 is used to supplement the Instrument Air System from the Station Air System.

Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 3E

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 066 Per SWI O-200.2, Control Room Access, who grants access to Areas A, B, & D?

a. Operations Manager ONLY

b. ANY Duty Licensed Operator

c. Operator at the Controls ONLY

d. Duty Shift Supervisor OR Duty Shift Manager ANSWER C

REFERENCE:

SWI O-200.2, pgs 3-4.

NEW MEMORY K/A: 2.1.13: Conduct of Operations: Knowledge of facility requirements for controlling vital/controlled access.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes OM is only person who can grant CR access.

b. Incorrect. Plausible as any DLO can grant access to CR RESTRICTED areas, but not PROHIBITED areas.

c. Correct. Only the OAC can grant access to CR PROHIBITED areas.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY

d. Incorrect. Plausible as DSM and DSS can grant CR RESTRICTED area access, but not PROHIBITED area access.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-201 Obj. 5

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 067 Letdown Flow is required to be LESS than...

a. 60 GPM to prevent flashing at the letdown orifices.

b. 60 GPM to limit pressure drop across the ion exchanger resin retention screens.

c. 90 GPM to prevent flashing at the letdown orifices.

d. 90 GPM to limit pressure drop across the ion exchanger resin retention screens.

ANSWER D

REFERENCE:

1C12.1, page 5 BANK MEMORY K/A: 2.1.32: Conduct of Operations: Ability to explain and apply system limits and precautions.

JUSTIFICATION:

a. Incorrect. Plausible as 60 gpm is a single charging pump flow limit and letdown flashing is a system precaution that is prevented by stopping letdown flow before stopping charging flow.

b. Incorrect. Plausible as 60 gpm is a single charging pump flow limit and limiting the pressure drop is the correct reason for the 90 gpm limit.

c. Incorrect. Plausible as 90 gpm is the correct letdown flow limit and if examinee incorrectly confuses reasons for system limitations.

d. Correct. 1C12.1 Limitation 5.3 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-001A Obj. 6

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 068 Unit 1 is in MODE 6, Refueling.

RCS boron concentration is 2200 ppm.

Refueling Water Cavity Water Level is 753'.

VCT boron concentration is 1900 ppm.

RWST boron concentration is 2300 ppm.

ALL RHR flow has been stopped to aid refueling.

The crew wants to RAISE refueling pool level by 1".

Which makeup sources to the RCS are acceptable?

VCT RWST RMU Tanks

a. Acceptable Acceptable Acceptable

b. Acceptable Acceptable NOT Acceptable

c. NOT Acceptable Acceptable NOT Acceptable

d. Acceptable NOT Acceptable NOT Acceptable ANSWER C

REFERENCE:

TS 3.9.5 BANK HIGHER K/A: 2.1.36: Conduct of Operations: Knowledge of procedures and limitations involved in core alterations.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes T.S. 3.9.5 does not apply due to water level; however, normal refueling water level is greater than 20 ft above the reactor vessel flange (752'8").

b. Incorrect. Plausible as RWST boron concentration is greater than the minimum of 2000 ppm required by TS 3.9.5 and COLR; however, in this case D5.2 does not allow use of water with boron concentration less than current RCS boron concentration.

c. Correct.

d. Incorrect. Plausible as RMU tank is not acceptable; however, RWST is acceptable because it is greater than 2200 ppm.

Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-0033 Obj. 9C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 069 Reactor startup preparations are in progress.

Shutdown Bank A is at 0 steps.

Shutdown Bank A is required to be at 228 steps per 1C5, Control Rod and Rod Position Indication Systems.

What positions will the Reactor Operator place the ROD BANK SELECTOR SWITCH AND the DIGITAL ROD CONTROL LEVER to obtain the required position on Shutdown Bank A?

ROD BANK DIGITAL ROD SELECTOR CONTROL

a. SBA IN

b. SBA OUT

c. MANUAL IN

d. MANUAL OUT ANSWER B

REFERENCE:

1C5, page 13 OE-186920, Movement of Control Rod Bank A with Bank Selector Switch in the Shutdown Bank A Position.

NEW HIGHER K/A: 2.2.1: Equipment Control: Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

JUSTIFICATION:

a. Incorrect. Plausible as RBS will be in SBA position; also if examinee incorrectly believes DRC lever must be positioned to IN to withdraw control rods.

b. Correct.

c. Incorrect. Plausible as RBS switch is normally in MANUAL and if examinee incorrectly believes shutdown banks will move with RBS switch in MANUAL; however, in this case only control banks will move. Also if examinee incorrectly believes DRC lever must be positioned to IN to withdraw control rods.

d. Incorrect. Plausible as DRC lever will be placed to OUT and RBS switch is normally in MANUAL; however, in this case shutdown banks will NOT move with RBS switch in MANUAL. Only control banks will move.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-005 Obj. 4

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 070 A load change from 50% to 100% is temporarily suspended.

SP 1005, NIS Power Range Daily Calibration, is being performed.

Reactor Thermal Power has been stable at 70.2% for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Nuclear Instruments are reading as follows:

o N41 is 72.6%.

o N42 is 70.4%.

o N43 is 70.8%.

o N44 is 69.6%.

Which Nuclear Instrument(s) REQUIRE(s) a gain adjustment?

a. ONLY N41

b. ONLY N44

c. N41 AND N43

d. N41 AND N44 ANSWER D

REFERENCE:

SP 1005 page 3 NEW HIGHER K/A: 2.2.12: Equipment Control: Knowledge of surveillance procedures.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes N41 is the only NI needing adjustment because it is the highest reading NI; however, N44 also needs adjustment because it is lower than RTP.

b. Incorrect. Plausible if examinee incorrectly believes N44 is the only NI needing adjustment because it is the lowest reading NI; however, N41 also needs adjustment because it exceeds RTP by greater than 2%.

c. Incorrect. Plausible if examinee incorrectly believes only NIs ABOVE.5% of RTP require adjustment.

d. Correct. Per the precautions and limitations of SP 1005: If this surveillance procedure is performed during reduced power as a result of load follow operation, then perform NIS gain adjustment if NIS indicated power is less than reactor thermal power or if NIS indicated power exceeds reactor thermal power by greater than 2%.

Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-002 Obj. 11

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 071 TS LCO 3.4.2, RCS Minimum Temperature for Criticality, states:

Each RCS loop average temperature (Tavg) shall be = __(1)__.

TS LCO 3.4.2 Condition A, Tavg in one or more RCS loops not within limit, Required Action and Completion Time states:

Be in MODE 2 with Keff < 1.0 __(2)__.

a. (1) 540°F; (2) immediately

b. (1) 540°F; (2) within 30 minutes

c. (1) 547°F; (2) immediately

d. (1) 547°F; (2) within 30 minutes ANSWER B

REFERENCE:

T.S. 3.4.2 NEW MEMORY K/A: 2.2.38: Equipment Control: Knowledge of conditions and limitations in the facility license.

JUSTIFICATION:

a. Incorrect. Plausible as the minimum temperature for criticality is 540F; however, Condition A does not state to reduce power to Mode 2 with keff less than 1.0 IMMEDIATELY.

b. Correct.

c. Incorrect. Plausible if the examinee incorrectly believes the minimum temperature is 547F instead of 540F and incorrectly believes the required action must be performed immediately.

d. Incorrect. Plausible as 547F is the minimum temperature for operations; however, it is not the minimum temperature for criticality per TS LCO 3.4.2.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj. 6

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 072 The crew is in 1C4, AOP2, Steam Generator Tube Leak.

The tube leak is on 11 Steam Generator.

Chemistry recommends MINIMIZING Steam Generator Blowdown flow from 11 Steam Generator.

Picture of Unit 1 Steam Generator Blowdown Flow controllers provided below:

The crew will adjust __(1)__ until Steam Generator Blowdown Flow controller OUTPUT indicates __(2)__.

a. (1) CV-31414; (2) 0%

b. (1) CV-31414; (2) 100%

c. (1) CV-31415; (2) 0%

d. (1) CV-31415; (2) 100%

ANSWER A

REFERENCE:

1C4 AOP2, page 18 NEW MEMORY K/A: 2.3.11: Radiation Control: Ability to control radiation releases.

JUSTIFICATION:

a. Correct.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY

b. Incorrect. Plausible as CV-31414 is the correct valve and if examinee incorrectly believes SGB is a reverse acting controller.

c. Incorrect. Plausible as the output will be adjusted to 0% and if examinee incorrectly believes CV-31415 is for 11 SG.

d. Incorrect. Plausible if examinee incorrectly believes CV-31415 is for 11 SG and that SGB is a reverse acting controller.

Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-002 Obj. 4D

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 073 Unit 1 was tripped from 100% power.

11 Steam Generator is FAULTED to containment.

Auxiliary Feedwater is isolated to 11 Steam Generator.

The basis for isolating Auxiliary Feedwater is to minimize the...

a. potential for Steam Generator overfill.

b. potential of rupturing a Steam Generator tube.

c. cooldown capability of the non-faulted Steam Generator.

d. RCS cooldown and mass and energy release from the faulted Steam Generator.

ANSWER D

REFERENCE:

1E-2 bases, page 2 BANK MEMORY K/A Number: 2.4.18: Emergency Procedures / Plan: Knowledge of the specific bases for EOPs.

JUSTIFICATION:

a. Incorrect. Plausible if the examinee incorrectly believes that feed will continue to increase SG level as it does during a normal Rx Trip.

b. Incorrect. Plausible as rupturing a SG tube is a concern for re-initiation of AFW, but is not a concern when securing AFW flow.

c. Incorrect. Plausible if examinee incorrectly believes that isolating AFW minimizes the cooldown capability rather than maximizing it. The temperature differential across the non-faulted S/G would increase when feedwater was isolated to a faulted S/G since they would be removing a larger decay heat load.

d. Correct.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 33.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 074 In accordance with the Emergency Plan, which of the following is responsible for performing ONSITE EMERGENCY RADIATION SURVEYS when Radiation Protection personnel are NOT available?

a. Security Group

b. Operations Group

c. Engineering Group

d. Maintenance Group ANSWER B

REFERENCE:

E-PLAN, pages 32, 35, and 36 NEW MEMORY K/A: 2.4.29: Emergency Procedures / Plan: Knowledge of the emergency plan.

JUSTIFICATION:

a. Incorrect. Plausible as security is responsible for personnel accountability and communication efforts.

b. Correct.

c. Incorrect. Plausible as engineering is responsible for core analysis and tech support for emergency repairs.

d. Incorrect. Plausible as maintenance is responsible for repair in support of emergency and recovery actions and supporting search and rescue efforts.

Proposed references to be provided to applicants during examination: None Learning Objective: P7405L-001 Objs 2 & 3

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 075 The Control Room has been evacuated.

Unit 1 and Unit 2 are being cooled down per C1.3 AOP2, Cooldown from Outside the Control Room.

The Shift Supervisor has directed the crew to maintain a 50°F/hour cooldown rate.

Unit 1 cooldown rate is 30°F/hour.

Unit 2 cooldown rate is 70°F/hour.

Picture of Train A Hot Shutdown Panel SG PORV controllers provided below:

Question continued on next page.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY Question continued from previous page.

How will the Reactor Operator adjust the output on 11 and 21 SG PORVs to maintain the required 50°F/hour cooldown rate?

CV-31084, 11 SG PORV CV-31102, 21 SG PORV

a. LOWER LOWER

b. LOWER RAISE

c. RAISE LOWER

d. RAISE RAISE ANSWER C

REFERENCE:

1C1.3 AOP2, page 17 2C1.3 AOP2, page 17 NEW HIGHER K/A: 2.4.34: Emergency Procedures / Plan: Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.

JUSTIFICATION:

a. Incorrect. Plausible as 21 SG PORV output will be lowered; however, in this case 11 SG PORV output must be raised.

b. Incorrect. Plausible if examinee incorrectly believes lowering output on 11 will raise CDR and raising output on 21 will lower CDR based on deviation meter indications.

c. Correct.

d. Incorrect. Plausible as 11 output will be raised; however, in this case 21 output must be lowered.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-248 Obj. 5

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 076 A small break LOCA has occurred on Unit 1.

The crew has stopped the 11 Safety Injection Pump per 1ES-1.1, Post LOCA Cooldown and Depressurization.

The crew observes the following indications:

Containment pressure is 7 psig.

RCS subcooling is 30°F.

Pressurizer level is 25% and lowering.

The Shift Supervisor will direct the crew to __(1)__ AND will __(2)__.

a. (1) manually start 11 Safety Injection Pump; (2) remain in 1ES-1.1, Post LOCA Cooldown and Depressurization

b. (1) manually start 11 Safety Injection Pump; (2) transition to 1E-1, Loss of Reactor or Secondary Coolant

c. (1) actuate Safety Injection; (2) remain in 1ES-1.1, Post LOCA Cooldown and Depressurization

d. (1) actuate Safety Injection; (2) transition to 1E-1, Loss of Reactor or Secondary Coolant ANSWER A

REFERENCE:

1ES-1.1 info page BANK HIGHER K/A: 009A215: Small Break LOCA: Ability to determine or interpret the following as they apply to a small break LOCA: RCS parameters.

JUSTIFICATION:

a. Correct. Per the Information Page, SI Reinitiation Criteria is met with ADVERSE containment conditions for inability to maintain Przr level >27%.

b. Incorrect. Plausible as SI is initiated by manually starting pumps; however, 1E-1 will not be entered.

c. Incorrect. Plausible as SI is required and the SS will remain in 1ES-1.1; however, SI cannot be initiated by actuating SI until RTBs have been cycled. SI is initiated by manually starting pumps.

d. Incorrect. Plausible as SI is required; however, in this case SI cannot be initiated by actuating SI until RTBs have been cycled and the SS will remain in 1ES-1.1.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 17.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 077 The following values were recorded per SP 1015, 4KV Bus 11/12 Undervoltage and Underfrequency Relay Test:

SP 1015 is provided.

The Shift Supervisor will declare BUS 11 RELAY INOPERABLE.

a. 27R

b. 27S

c. 81A

d. 81B ANSWER D

REFERENCE:

SP 1015, pages 80-84 TS Table 3.3.1-1, function 11b NEW HIGHER K/A: 15/17 2.1.12: RCP Malfunctions: Knowledge of surveillance procedures.

JUSTIFICATION:

a. Incorrect. Plausible as relay 27R D.O. voltage is < acceptable range but > TS limit.

b. Incorrect. Plausible as relay 27S P.U. voltage is < acceptable range; however, in this case no TS limit applies.

c. Incorrect. Plausible as relay 81A U.F. is > acceptable range but not < TS limit.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY

d. Correct. Relay 81B is < acceptable range and < TS limit.

Proposed references to be provided to applicants during examination: SP 1015 Learning Objective: P8170L-002 Obj 10C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 078 Unit 1 is in Mode 3, HOT STANDBY.

11 and 12 RCPs are running.

The RCP indications on Panel B (CVCS Letdown) are as follows:

Question continued on next page.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY Question continued from previous page.

The CC indications of Panel A (Component Cooling) are as follows:

After completing the actions of the appropriate AOP, the Shift Supervisor will declare INOPERABLE.

a. ONLY the "A" RCS loop

b. ONLY the "B" RCS loop

c. BOTH RCS Loops

d. NEITHER RCS Loops ANSWER A

REFERENCE:

1C3 AOP2 page 4 1C12 AOP1 page 4 TS LCO 3.4.5 MODIFIED HIGHER K/A: 022A2.02: Loss of Reactor Coolant Makeup: Ability to determine and interpret the following as they apply to the Reactor Coolant Makeup: Charging pump problems.

JUSTIFICATION:

a. Correct. 11 RCP has lost seal cooling (Seal injection and CC to the bearings); therefore, 11 RCP will be secured per 1C3 AOP2. Once 11 RCP is secured, the "A" RCS Loop is INOPERABLE per T.S. 3.4.5.

b. Incorrect. Plausible if examinee incorrectly believes seal cooling is lost to the 12 RCP based on 12 RCP CC outlet temperature.

c. Incorrect. Plausible if examinee incorrectly believes both RCPs will be stopped based on loss of seal injection flow alone. This is incorrect per 1C12.1 AOP1.

d. Incorrect. Plausible if examinee is not familiar or does not recognize 11 RCP has exceeded the bearing water temperature limit of 200F and determines NO RCPs need to be tripped at this time.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-002 Obj. 3H

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 079 The crew is on step 5 of 1ECA-0.0, Loss of All Safeguards AC Power.

Bus 16 green load rejection lights are LIT.

Bus 16 lock out annunciator 47024-0104 is OFF.

Bus 15 green load rejection lights are NOT LIT.

Bus 15 lock out annunciator 47024-0101 is OFF.

11 Turbine Driven AFW Pump tripped on overspeed.

RED PATH exists on HEAT SINK Critical Safety Function.

1ECA-0.0 is provided.

The Shift Supervisor will...

a. direct out-plant operators to isolate RCP seals.

b. transition to 1FR-H.1, Response to Loss of Secondary Heat Sink.

c. direct the Lead RO to energize Bus 15 from D1 Emergency Diesel Generator.

d. direct the Lead RO to energize Bus 16 from D2 Emergency Diesel Generator.

ANSWER D

REFERENCE:

1ECA-0.0, page 3 NEW HIGHER K/A: 055 2.4.20: Station Blackout: Knowledge of the operational implications of EOP warnings, cautions, and notes.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that neither bus is available.

b. Incorrect. Plausible if examinee incorrectly believes a transition to FR-H.1 is appropriate; however, in this case ECA-0.0 NOTE prior to step 1 states CSF trees are for indication only and FR procedures shall NOT be implemented.

c. Incorrect. Plausible if examinee incorrectly believes Bus 15 is available and Bus 16 is not.

d. Correct.

Proposed references to be provided to applicants during examination: 1ECA-0.0 (DO NOT GIVE BASES)

Learning Objective: P8140L-247 Obj. 3 & 8

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 080 A Loss of Offsite Power has occurred.

Unit 1 is in MODE 3.

The Shift Supervisor has entered TS LCO 3.8.1 Condition A and C.

11 TD AFW Pump trips on overspeed.

CV-31059, 11 AFWP TURBINE TRIP/THROTTLE VALVE, can NOT be reset.

It will take 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to repair 11 TD AFW Pump.

TS LCO 3.7.5 and TS LCO 3.8.1 are provided.

The Shift Supervisor will enter TS LCO 3.7.5.

a. Condition A ONLY

b. Condition B ONLY

c. Condition A and D

d. Condition B and D ANSWER B

REFERENCE:

TS LCO 3.7.5 TS LCO 3.8.1 TS BASES, pages B 3.8.1-11 thru B 3.8.1-13.

NEW HIGHER K/A: 056A2.07: Loss of Offsite Power: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Operational status of emergency feedwater pump (motor driven).

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes the trip/throttle valve is a steam supply for 11 TDAFWP.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly believes 12 MDAFWP is also not available.

d. Incorrect. Plausible as Cond B will be entered and if examinee incorrectly believes 12 MDAFWP is also not available.

Proposed references to be provided to applicants during examination: TS LCO 3.7.5 and TS LCO 3.8.1 Learning Objective: P8180L-007 Obj. 10C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 081 Per C20.3, Electrical Power System Security Analysis:

345 KV Bus Voltage Setpoint is 341.9 Kv.

161 KV Bus Voltage Setpoint is 160.5 Kv.

345 KV Bus 2 Voltage is 372.5 Kv.

161 KV Voltage is 159.8 Kv.

Bus 15 Voltage is 4097v.

Bus 16 Voltage is 4501v.

The Shift Supervisor will declare the (1) source and Bus (2) INOPERABLE.

a. (1) R; (2) 15

b. (1) R; (2) 16

c. (1) CT; (2) 15

d. (1) CT; (2) 16 ANSWER B

REFERENCE:

C20.3, pg. 7 1C20.5, pg. 4 NEW HIGHER K/A Number: 077 2.2.36: Generator Voltage and Electric Grid Disturbances Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

JUSTIFICATION:

a. Incorrect. Plausible as the R source will be inoperable and if examinee incorrectly believes Bus 15 voltage is below the 4KV limit.

b. Correct. Per C20.3, 345KV voltage high limit is 362KV. If >362KV, and 4KV >4400v or if

<4000v then 4KV bus is inoperable.

c. Incorrect. Plausible if examinee incorrectly believes Bus 15 is below the 4KV limit and that the CT source is supplied by Bus 2.

d. Incorrect. Plausible as Bus 16 is inoperable and if examinee incorrectly believes the CT source is supplied by Bus 2.

Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-008 090 Obj. 6

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 082 Unit 1 Instrument Air Header has depressurized.

The reactor was manually tripped.

ONLY ONE Charging Pump is available.

11 and 12 RCP seal flows are 8 gpm.

Control Rods G11 and H8 are stuck at 100 steps.

The crew is performing 1ES-0.1, Reactor Trip Recovery.

The Shift Supervisor will direct the crew to add (1) gallons of boric acid per (2).

a. (1) 400; (2) 1C12.5, Unit 1 Boron Concentration Control

b. (1) 400; (2) C12.5 AOP1, Emergency Boration of the Reactor Coolant System

c. (1) 800; (2) 1C12.5, Unit 1 Boron Concentration Control

d. (1) 800; (2) C12.5 AOP1, Emergency Boration of the Reactor Coolant System ANSWER D

REFERENCE:

1ES-0.1 page 5 C12.5 AOP1 pages 1 - 7 MODIFIED HIGHER K/A: 024A2.05: Emergency Boration: Ability to determine and interpret the following as they apply to the Emergency Boration: Amount of boron to add to achieve required SDM.

JUSTIFICATION:

a. Incorrect. Plausible if examinee does not recognize loss air impact on the normal boration system and does not know appropriate boration for SDM of 400 gal per stuck rod.

b. Incorrect. Plausible if examinee recognizes emergency boration is available but does not know appropriate boration for SDM of 400 gal per stuck rod.

c. Incorrect. Plausible if examinee correctly chooses appropriate boration amount but does not recognize impact from loss of instrument air on normal boration system.

d. Correct. Due to the loss of IA the charging line flow control valve is failed closed therefore ALL charging is via the seals. Maximum boric acid concentration is limited to 75% of flow so with 8 gpm charging per seal only 12 gpm flow of boric acid would be maximum allowed per C12.5 AOP1. This flowpath is required since IA has been lost.

Proposed references to be provided to applicants during examination: None.

Learning Objective: P8140L-225 Obj. A.1 For C12.5 AOP1, Emergency Boration of the Reactor Coolant System, explain the purpose and sequence of major steps.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 083 Unit 1 is at 5% power.

A Unit 1 Reactor Startup is in progress.

N35, Intermediate Range Nuclear Instrument, is declared INOPERABLE.

TS LCO 3.3.1 is provided.

The Shift Supervisor will enter TS LCO 3.3.1 Condition A and Condition.

a. C

b. D

c. F

d. Q ANSWER C

REFERENCE:

TS LCO 3.3.1, pgs. 3.3.1-1 thru 3.3.1-9, 3.3.1-17 NEW HIGHER K/A: 033 2.2.38: Loss of Intermediate Range Nuclear Instrumentation: Knowledge of conditions and limitations in the facility license.

JUSTIFICATION:

a. Incorrect. Plausible as condition C is entered for one channel inoperable; however, condition C only applies for manual reactor trip.

b. Incorrect. Plausible as condition D is entered for power range NI failures because of there impact on OTDT and OPDT. However, for intermediate range NI failures, it is not because the Intermediate range NI instruments do NOT provide any inputs into OTDT or OPDT.

c. Correct. Since reactor power is above P-6 and below P-10, table 3.3.1-1 references Condition F and G. Since only one IR NI is OOS, only Condition F is applicable.

d. Incorrect. Plausible if examinee incorrectly believes reactor power is below the P-6 setpoint and references Condition Q per Table 3.3.1-1; however, reactor power is above the P-6 setpoint.

Proposed references to be provided to applicants during examination: TS LCO 3.3.1 Learning Objective: P8184L-002 Obj. 10.C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 084 The fire protection sprinkler system for the D1 and D2 Emergency DieselGenerator Area was declared NOT functional.

What compensatory actions are required to be established for the D1 and D2 Area?

Type of Fire Watch Backup Fire Suppression Required (if any) Required

a. Hourly No

b. Continuous No

c. Continuous Yes

d. Not Required Yes ANSWER C

REFERENCE:

F5 APP K pages 12, 15, 21, and 28.

NEW MEMORY K/A: 067A2.15: Plant Fire on Site: Ability to determine and interpret the following as they apply to the Plant Fire on Site: Requirements for establishing a fire watch.

JUSTIFICATION:

a. Incorrect. Plausible as these are the compensatory actions for a fire detection zone being not functional (Section 7.2 of F5 APP K).

b. Incorrect. Plausible as these are the compensatory actions for a fire barrier being not functional (Section 7.17 of F5 APP K).

c. Correct. Per Section 7.7 of F5 APP K, if a fire protection sprinkler system is not functional for the D1 and D2 Diesel Generator areas, then a continuous fire watch with backup fire suppression equipment shall be established within one hour.

d. Incorrect. Plausible as these are the compensatory actions for all fire pumps being impaired (Section 7.4.3 of F5 APP K).

Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-002 Obj. 15

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 085 The Unit 1 reactor tripped from 100% power 30 minutes ago.

Containment pressure is 4 psig.

Containment Sump Level is 4.2 FT.

1R48, Unit 1 Containment High Range Area Monitor, is reading 250 R/HR.

1R49, Unit 1 Containment High Range Area Monitor, is reading 190 R/HR.

One Containment Spray Pump is RUNNING.

F-0.5, Critical safety Function Status Tree - CONTAINMENT, is provided below.

CONTAINMENT Critical Safety Function is CURRENTLY.

a. GREEN

b. YELLOW

c. ORANGE

d. RED ANSWER B

REFERENCE:

1F-0, pages 3 & 4

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 1F-0.5, page 1 NEW HIGHER K/A: 2.4.45: E16 High Containment Radiation: Ability to prioritize and interpret the significance of each annunciator or alarm.

JUSTIFICATION:

a. Incorrect. Plausible as one CTMT rad monitor is less than 200 r/hr and sump level is less than 8 ft; however, in this case the highest reading rad monitor would be used.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly believes CTMT pressure is >23 psig and either sump level is >8 ft OR no CTMT spray pumps are running.

d. Incorrect. Plausible if examinee incorrectly believes CTMT pressure is > 46 psig.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 39 & 40.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 086 A rupture occurred on the Unit 1 Component Cooling Water piping.

1C14 AOP1, Loss of Component Cooling, was entered.

Unit 1 CC Surge Tank level cannot be maintained on scale.

1E-0, Reactor Trip or Safety Injection, was entered.

Containment Pressure is rapidly rising.

Safety Injection was manually actuated.

Immediate Actions of 1E-0 are completed.

The Shift Supervisor will ensure the crew performs...

a. 1E-0 and 1C14 AOP1 concurrently.

b. 1C14 AOP1 to completion; then resume 1E-0.

c. 1E-0 to completion; then resume 1C14 AOP1.

d. 1E-0 exclusively and NOT complete 1C14 AOP1.

ANSWER A

REFERENCE:

1C14 AOP1 page 5.

BANK HIGHER K/A: 008 2.4.8: Component Cooling Water System (CCWS): Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

JUSTIFICATION:

a. Correct. Subsequent manual actions of 1C14 AOP1 (step 2.4.1) states, "If at any time the level in the CC Surge Tank cannot be maintained "on scale" OR CC flow cannot be maintained, then trip the reactor, then initiate 1E-0 AND complete the remaining steps of this procedure."

b. Incorrect. Plausible if examinee incorrectly prioritizes 1C14 AOP1 over 1E-0 actions. This is incorrect because a LOCA or Steam Line Break is occurring (as indicated by containment pressure rising and SI being manually actuated).

c. Incorrect. Plausible as 1E-0 will be initiated and performed; however, 1C14 AOP1 needs to be performed in parallel. 1C14 AOP1 has actions to secure safeguards equipment during a loss of CC.

d. Incorrect. Plausible if examinee incorrectly believes that AOPs are no longer implemented after entering the EOP network.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140S-200 ATT 27 Obj. 6C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 087 Unit 2 is in Mode 3.

A significant amount of water is discovered around 22 CFCU.

A water sample determines the water is from the river.

All actions of C35 AOP4, Cooling Water Leakage in Containment, are complete.

What is the OPERABILITY status of Containment and 22 CFCU?

Containment 22 CFCU

a. OPERABLE OPERABLE

b. OPERABLE INOPERABLE

c. INOPERABLE OPERABLE

d. INOPERABLE INOPERABLE ANSWER B

REFERENCE:

C35 AOP4 page 6 NEW HIGHER K/A: 022A2.05: Containment Coolingz: Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Major leak in CCS.

JUSTIFICATION:

a. Incorrect. Plausible if examinee does not realize the impact on the leak has on the containment boundary and incorrectly believes the CFCU is still operable because it still provides cooling. If the stem was changed such that, "A water sample determines the water is from condensation" would make "a" the correct answer.

b. Correct. Once C35 AOP4 actions are complete, CTMT is restored to operable but 22 CFCU is still inoperable until leak is fixed.

c. Incorrect. Plausible if examinee incorrectly believes C35 AOP4 actions will render 22 CFCU operable and CTMT inoperable.

d. Incorrect. Plausible as both would be inoperable if no operator actions are taken.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009H Obj. 10D

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 088 Unit 1 tripped due to a spurious actuation of Containment Isolation.

Both Feedwater Containment Isolation valves could NOT be re-opened after resetting the Containment Isolation signal.

Both RCPs are running.

RVLIS Dynamic Range Level is 95% and stable.

Core Exit Thermocouples are 620°F and stable.

NO AFW pumps are available for Unit 1.

11 and 12 SG Wide Range levels are 4% and lowering.

The Shift Supervisor will enter (1) and direct the crew to (2).

a. (1) 1FR-C.2, Response to Degraded Core Cooling; (2) start safety injection pumps

b. (1) 1FR-C.2, Response to Degraded Core Cooling; (2) depressurize the SGs to inject accumulators

c. (1) 1FR-H.1, Response to Loss of Secondary Heat Sink; (2) block SI and depressurize at least one SG.

d. (1) 1FR-H.1, Response to Loss of Secondary Heat Sink; (2) stop RCPs and establish RCS feed and bleed ANSWER D

REFERENCE:

1FR-H.1 pages 2, 3, 8 1F-0.2, 1F-0.3 1FR-C.2 pages 3 and 10.

NEW HIGHER K/A: 061A2.09: Auxiliary / Emergency Feedwater (AFW) System: 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: A total loss of feedwater.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes entry conditions exist for entry into FR-C.2. Also plausible as the conditions listed do require starting safety injections pumps to establish bleed and feed. Although RVLIS level is lower than normal and CETC are higher than normal, entry conditions for degraded core cooling are not met because RVLIS level would need to drop below 62% or CETC would need to be above 700F.

b. Incorrect. Plausible if examinee incorrectly believes entry conditions exist for entry into FR-C.2. Depressurizing the SGs is also a correct step for a loss of heat sink if SG WR levels were higher. The depressurizing of SGs is performed to support establishing feed with the condensate system. Although RVLIS level is lower than normal and CETC are higher than normal, entry conditions for degraded core cooling are not met because RVLIS level would need to drop below 62% or CETC would need to be above 700F.

c. Incorrect. Plausible as entering FR-H.1 is the correct procedure and blocking SI and depressurizing at least one SG is an action contained in FR-H.1. However, since SG WR

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY level is below 9%, FR-H.1 requires bleed and feed to be established.

d. Correct. Since both SG WR levels are below 50%, entry into FR-H.1 is met. Entry conditions for FR-C.2 are not met. Since both SG WR levels are below 9%, step 2 of FR-H.1 requires stopping RCPs and establishing RCS bleed and feed.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 21 and 22.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 089 Both Units are at 100% power.

The following were declared INOPERABLE at the given times:

BKR 27-1, 121 MD CLG WTR PMP (SOURCE FROM BUS 26), at 0100.

22 Diesel Driven Cooling Water Pump at 0200.

11 Safeguards Screenhouse Exhaust Fan at 0300.

TS LCO 3.7.8 is provided.

The Shift Supervisor will enter TS LCO 3.7.8 Condition A at (1) and TS LCO 3.0.3 at (2).

a. (1) 0100; (2) 0200

b. (1) 0100; (2) 0300

c. (1) 0200; (2) 0300

d. (1) 0300; (2) 0300 ANSWER C

REFERENCE:

Tech Specs, pages 3.0-6 and 3.7.8-1 Tech Specs Bases, pages B 3.7.8 B 3.7.8-9 C18.1 page 22.

BANK HIGHER K/A: 2.2.40: 076 Service Water System (SWS): Ability to apply Technical Specifications for a system.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that LCO 3.7.8 Cond A is not met when 121 MD CLG Pump is unable to be aligned to the B header and incorrectly believes LCO 3.0.3 is met when 22 Diesel Driven Cooling water pump is inoperable due to 2 safeguards cooling water pumps being inoperable.

b. Incorrect. Plausible if examinee incorrectly believes that LCO 3.7.8 Cond A is met when 121 MD CLG Pump is unable to be aligned to the B header

c. Correct.

d. Incorrect. Plausible as LCO 3.0.3 will be entered at 0300; however, LCO 3.7.8 will be entered at 0200 instead of 0300. This is plausible if examinee incorrectly believes 121 Cooling water is still available to B header and incorrectly believes no spec condition for exhaust fan and therefore enters LCO 3.0.3.

Proposed references to be provided to applicants during examination: TS LCO 3.7.8 Learning Objective: P8176L-003 Obj. 10C

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 090 Unit 1 and Unit 2 are at 100% power.

Outside air temperature is 95°F.

An EQUALIZING charge is in progress on 11 Battery.

11, 12, 21, and 22 Battery Special Exhaust fans are RUNNING.

121 Battery Room Cooling Refrigeration Unit is IN SERVICE.

122 Battery Room Cooling Refrigeration Unit compressor catastrophically failed.

11 Battery Room temperature is 77°F and stable.

12 Battery Room temperature is 82°F and slowly rising.

21 Battery Room temperature is 84°F and slowly rising.

22 Battery Room temperature is 84°F and slowly rising.

A continuous fire watch is stationed in the Safeguard Battery Rooms.

1C18.1, Engineered Safeguards Equipment Support Systems, is provided.

The Shift Supervisor will direct the crew to block OPEN the following Battery Room Doors:

a. 224, 226, 228

b. 226, 227, 228

c. 224, 225, 226, 227

d. 224, 225, 226, 227, 228 ANSWER B

REFERENCE:

C18.1, page 35 C37.15, page 5

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY NEW HIGHER K/A: 063A2.02: DC Electrical Distribution System: Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical distribution systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of ventilation during battery charging.

JUSTIFICATION:

a. Incorrect. Plausible as doors 226 and 228 will be opened and if examinee incorrectly believes the turbine building door should be opened for ventilation; however, in this case door 224 is required to remain closed due to HELB concerns with MSIVs open.

b. Correct. 121 Battery Room Cooling Refrigeration Unit supplies 11 battery room. 122 Battery Room Cooling Refrigeration Unit supplies 12, 21 & 22 battery rooms. A loss of one requires opening battery room INTERNAL doors only for cooling. Both units MSIVs are open and turbine building to battery room doors cannot be blocked open due to HELB concerns.

c. Incorrect. Plausible if examinee incorrectly believes all battery room cooling was lost and turbine building doors should be opened for ventilation but train separation is still required; however, in this case doors 224 and 225 will remain closed due to HELB concerns and 11 battery room cooling still operating.

d. Incorrect. Plausible as all interior doors will be blocked open; also, exterior turbine doors 224 and 225 will be opened with compensatory measures if battery room temps reach 118°F.

Proposed references to be provided to applicants during examination: C18.1 Learning Objective: P8186L-005 Obj. 5d.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 091 Unit 1 is at 70% power.

A power increase was just completed one hour ago.

Control Bank D Rod Position and Group Counter is as follows:

TS LCO 3.1.7 is provided.

The Shift Supervisor will direct the performance of (1) once every (2) hours.

a. (1) flux mapping; (2) four

b. (1) flux mapping; (2) eight

c. (1) rod position indication hot calibration; (2) four

d. (1) rod position indication hot calibration; (2) eight ANSWER B

REFERENCE:

TS 3.1.7 SP 1018B, pg 2 SP 1319, pg 2.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY MODIFIED HIGHER K/A: 014 2.2.22: Rod Position Indication System (RPIS): Knowledge of limiting conditions for operations and safety limits.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes more than one RPI is inoperable.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly believes more than one RPI is inoperable and that the performance of this SP is allowed; however, in this case the SP is only performed once prior to criticality after each head removal.

d. Incorrect. Plausible as 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is the correct frequency; however, in this case the SP is only performed once prior to criticality after each head removal.

Proposed references to be provided to applicants during examination: TS 3.1.7.

Learning Objective: P8184L-005 Obj 10C.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 092 PINGP 1576, Emergency Action Level Matrix, is provided.

Based ONLY on the ERCS STAT screen above, what is the status of the following fission product barriers per the Emergency Action Level Matrix?

Fuel Cladding Containment

a. LOSS INTACT

b. LOSS POTENTIAL LOSS

c. POTENTIAL LOSS INTACT

d. POTENTIAL LOSS POTENTIAL LOSS ANSWER B

REFERENCE:

PINGP 1576, pg. 6 NEW HIGHER K/A: 028A2.02: Hydrogen Recombiner and Purge Control System (HRPS): Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS; and (b) based on

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: LOCA condition and related concern over hydrogen.

JUSTIFICATION:

a. Incorrect. Plausible as there is a loss of fuel cladding; however, Containment is NOT intact.

b. Correct. A loss of the fuel cladding barrier is indicated by the Core Cooling CSF being red and CETC reading above 1200F. A potential loss of Containment is indicated by Containment Hydrogen concentration being greater than 6%.

c. Incorrect. Plausible if examinee incorrectly believes there is only a potential loss of the Fuel cladding barrier due to CETC being above 700F, does not recognize the loss of fuel cladding due to CETC being above 1200F and does not recognize that Containment is potentially loss due to hydrogen concentration being above 6%. Examinee may incorrectly believe Containment is intact because the Containment (Z) CSF is green.

d. Incorrect. Plausible if examinee incorrectly believes there is a potential loss of the Fuel cladding barrier due to CETC being above 700F and does not recognize the loss of fuel cladding due to CETC being above 1200F. Also plausible if examinee mistakes the red path in Core Cooling (C) for a red path in Containment (Z).

Proposed references to be provided to applicants during examination: PINGP 1576 Learning Objective: P7410L-002 Obj 3

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 093 Unit 1 Steam Generators are blowing down to the river for chemistry control.

123 ADT Monitor Tank is being released to the river.

1R-19, SG BLOWDOWN MONITOR, is INOPERABLE.

R-18, LIQUID RELEASE MONITOR, is INOPERABLE.

Grab samples from Unit 1 Steam Generator Blowdown Effluent Line are being taken and analyzed every 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Two independent samples of the 123 ADT Monitor Tank was taken and analyzed.

All sample results are satisfactory.

A verification of the release rate calculation and discharge line valve lineup has NOT been performed for either of the releases.

Table 2.2 of H4, Offsite Dose Calculation Manual, is provided.

Using H4, determine if each of the releases must be suspended or may continue.

Unit 1 SG Blowdown 123 ADT Monitor Tank

a. MAY CONTINUE MAY CONTINUE

b. MAY CONTINUE MUST BE SUSPENDED

c. MUST BE SUSPENDED MAY CONTINUE

d. MUST BE SUSPENDED MUST BE SUSPENDED ANSWER B

REFERENCE:

H4, Table 2.2 BANK HIGHER K/A: 068A2.04: Liquid Radwaste System (LRS): Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation.

JUSTIFICATION:

a. Incorrect. Plausible as the Unit 1 SG Blowdown release may continue; however, the release of 123 ADT Monitor Tank must be suspended. Examinee may incorrectly believe the release of 123 ADT Monitor Tank may continue because two independent samples of the tank were taken and analyzed; however, a verification of the release rate calculation and discharge line valve lineup must also be performed.

b. Correct.

c. Incorrect. Plausible if the examinee incorrectly believes two independent samples of both sources of the releases must be performed and analyzed and that is the only requirement regardless of the source.

d. Incorrect. Plausible as the release from 123 ADT Monitor Tank must be suspended; however, the release of the Unit 1 SG Blowdown may continue. Examinee may incorrectly believe the release of Unit 1 SG blowdown must be suspended if they apply action 1 criteria

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY instead of action 2 criteria.

Proposed references to be provided to applicants during examination: H4, Table 2.2 Learning Objective: P8182L-001A Obj. 11

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 094 A HOSTILE ACTION has occurred in the Protected Area.

The Shift Manager has declared a General Emergency.

Meteorological data from ERCS is as follows:

PINGP 577, Emergency Notification Report Form, is provided.

The initial PAR will recommend (1) sectors out to 2 miles and (2) sectors from 2-5 miles.

a. (1) SHELTER ALL; (2) EVACUATE ALL

b. (1) SHELTER ALL; (2) EVACUATE DOWNWIND

c. (1) EVACUATE ALL; (2) EVACUATE ALL

d. (1) EVACUATE ALL; (2) EVACUATE DOWNWIND ANSWER A

REFERENCE:

PINGP 577 BANK HIGHER K/A: 2.1.18: Conduct of Operations: Ability to make accurate, clear, and concise logs, records, status boards, and reports.

JUSTIFICATION:

a. Correct.

b. Incorrect. Plausible as the PAR will recommend sheltering out to 2 miles; however, it will NOT recommend only evacuating downwind sectors from 2-5 miles. Also plausible if examinee does not recognize wind speed is less than 5 mph.

c. Incorrect. Plausible as the PAR will recommend evacuating all sectors from 2-5 miles; however, it will not recommend evacuating all sectors out to 2 miles. Also plausible if

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY examinee does not recognize HAB event.

d. Incorrect. Plausible if examinee does not recognize HAB event and does not recognize that wind speed is less than 5 mph.

Proposed references to be provided to applicants during examination: PINGP 577 Learning Objective: P7410L-034 Obj 7

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 095 Refueling in Containment is in progress.

A fuel bundle is being transferred from the containment upender to the core.

The Containment SRO loses communication with the Control Room.

The SRO will...

a. suspend the transfer, reestablish communication, then recommence the transfer.

b. return the fuel bundle to the upender THEN reestablish communication.

c. complete the transfer of the fuel bundle to the core THEN reestablish communication prior moving the next fuel bundle.

d. lower the fuel bundle to the bottom of the refueling pool, reestablish communication, THEN recommence the transfer.

ANSWER A

REFERENCE:

D5.2 page 5.

NEW MEMORY K/A: 2.1.35: Conduct of Operations: Knowledge of fuel handling responsibilities of SROs.

JUSTIFICATION:

a. Correct. Per D5.2, Fuel movement in the Containment SHALL be suspended in the event of loss of communication between the Control Room and containment.

b. Incorrect. Plausible if examinee incorrectly believes the fuel bundle must be placed back where it came from prior to suspending fuel movement.

c. Incorrect. Plausible if examinee incorrectly believes the procedure allows the fuel handling team to complete the current transfer prior to suspending fuel handling.

d. Incorrect. Plausible if examinee incorrectly believes the fuel manipulator crane can NOT be under any load prior to suspending the fuel movement.

Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-003 Obj. 10

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 096 Unit 1 ERCS indicates the following:

PINGP 1102, Unit 1 Shutdown Safety Assessment, is provided.

Question continued on next page.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY Question continued from previous page.

The Unit 1 480 Volt Power Availability Shutdown Safety Condition is.

a. GREEN

b. YELLOW

c. ORANGE

d. RED ANSWER B

REFERENCE:

PINGP 1102, pgs. 1 & 7 NEW HIGHER K/A: 2.2.18: Equipment Control: Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes that Bus 111 is considered available for Shutdown Safety Assessment; however, since Bus 111 is being supplied from unit 2, it is not considered available. Also plausible if examinee incorrectly applies 1 point for Bus 111 based only on its voltage being in the range of 420 and 505 volts.

b. Correct. Since BKR 111M is open, no points are given for Bus 111 Energized from Bus 15.

Three points are given for Bus 112, Bus 121, and Bus 122 being energized between 420 and 505 volts and aligned to Unit 1 Safeguards 4160 Buses. One more point is given since both train B 480 Buses are in there normal lineup. The total points are 4; which equates to the shutdown safety condition of YELLOW for 480V Power Availability per the chart on page 1 of PINGP 1102.

c. Incorrect. Plausible if examinee incorrectly gives no points for Bus configuration due to train A 480 Buses not being in there normal lineup AND misapplies the chart on page 1 of PINGP 1102 by considering 3 points an ORANGE condition.

d. Incorrect. Plausible if examinee confuses the indications on the ERCS screen and incorrectly believes three of the 480V buses are energized from there alternate (U2) supply and therefore only assigns one point total for 480V Availability; which equates to a RED condition.

Proposed references to be provided to applicants during examination: PINGP 1102 Learning Objective: None. However, this is a task in the Shift Supervisor OJT/TPE guide.

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 097 Given the following note from TS LCO 3.4.6:

2.

No RCP shall be started with any RCS cold leg temperature the Over Pressure Protection System (OPPS) enable temperature specified in the PTLR unless:

a.

The secondary side water temperature of each steam generator (SG) is 50°F above each of the RCS cold leg temperatures; or

b.

There is a steam or gas bubble in the pressurizer.

What is the basis for this restriction?

a. Prevent outsurge from emptying the pressurizer following an RCP start.

b. Minimize RCS pressure transient caused by heat transfer from a hot SG.

c. Minimize RCS pressure transient caused by additional heat transfer from the core.

d. Minimize RCS pressure transient due to additional RCP pressure head added to RCS pressure.

ANSWER B

REFERENCE:

T.S. LCO 3.4.6 T.S. 3.4.6 Bases BANK FUNDAMENTAL K/A: 2.2.25: Equipment Control: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

JUSTIFICATION:

a. Incorrect. Higher SG temperature will cause an insurge to the Pzr, due to expansion of the coolant.

b. Correct, see explanation above.

c. Incorrect. The RCS pressure transient will not be caused by heat transfer out of the core. It will be into the core.

d. Incorrect. RCP pressure head while increased will not cause a large pressure transient. The RCP head pressure will only be felt on the U-Tubes of the S/G.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-002 Obj 10D

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 098 Unit 1 is in MODE 6.

The Radiation Protection group is requesting access to Sump C.

All requirements are MET to enter Sump C.

The Shift Supervisor will issue Sump C keys to the Radiation Protection Supervisor after written permission is given by.

a. Shift Outage Manager AND Containment Coordinator

b. Plant Manager AND Radiation Protection Manager

c. Security Manager AND Facilities Supervisor

d. Operations Manager AND Shift Manager ANSWER B

REFERENCE:

5AWI 5.3.0, page 8 T.S. 5.7.2 F2, page 16 NEW HIGHER K/A: 2.3.13: Radiation Control: 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.

JUSTIFICATION:

a. Incorrect. Plausible as these positions control access to CTMT and if examinee incorrectly believes these positions also control access to Sump C.

b. Correct. Per F2, 5AWI 5.3.0, and T.S. 5.7.2, the SS must get written permission from PM and RPM prior to releasing LHRA keys to RP supervision.

c. Incorrect. Plausible as Sec. Mgr. and Fac. Sup. are listed in 5AWI 5.3.0 for issuing keys; also if examinee incorrectly believes these positions control all keys onsite.

d. Incorrect. Plausible as OM and SM permission required for plant keys and seals; however, in this case the LHRA and VHRA keys are administratively controlled by the PM and RPM.

Proposed references to be provided to applicants during examination: None Learning Objective: P9130L-003 Obj. 7

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 099 TIME 0100 Initial classification of FS1 declared.

0130 The Technical Support Center (TSC) is fully staffed and operational.

0140 The Operations Support Center (OSC) is fully staffed and operational.

0150 Classification change to FG1 is declared.

In accordance with the E-Plan, the was responsible for the OFF-SITE NOTIFICATIONS for the PAR at 0150.

a. Duty Shift Manager

b. Emergency Manager

c. Operations Group Leader

d. Designated Emergency Director ANSWER D

REFERENCE:

E-PLAN, page 20; F3-1, page 6.

NEW HIGHER K/A: 2.4.29: Emergency Procedures / Plan: Knowledge of the emergency plan.

JUSTIFICATION:

a. Incorrect. Plausible if examinee incorrectly believes the Duty Shift Manager is always responsible for offsite notifications. Initially, the Duty Shift Manager is the interim Emergency Director and has the responsibility of off-site notifications until the TSC is staffed.

b. Incorrect. Plausible if the examinee incorrectly believes the Emergency Director maintains the off-site notifications for the remainder of the event. The Emergency Director will assume responsibility of off-site notifications from the Shift Manager after the TSC is staffed.

c. Incorrect. Plausible if the examinee incorrectly believes the Operations Group Leader assumes the off-site notifications from the Emergency Director once the OSC is staffed and maintains that responsibility for the remainder of the event.

d. Correct. Once the EOF is staffed, the Emergency Manager assumes the responsibility of off-site notifications from the Emergency Director.

Proposed references to be provided to applicants during examination: None.

Learning Objective: P7410L-008 Obj 1

2016 NRC INITIAL LICENSE WRITTEN EXAM SENIOR REACTOR OPERATOR - KEY 100 Unit 1 is in MODE 6.

Refueling is in progress.

BKR 16-10, BUSTIE BUS16 / BUS 26, is Out of Service.

A LOSS OF ALL OFFSITE POWER occurs.

Bus 15 locks out.

D2 Emergency Diesel Generator trips on overspeed.

D2 and BKR 16-10 will take at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore.

RCS temperature is 160°F and stable.

Refueling inventory is at 370" and stable.

PINGP 1576, Emergency Action Level Matrix, is provided.

What is the HIGHEST emergency classification currently met?

a. Notification of Unusual Event

b. Alert

c. Site Area Emergency

d. General Emergency ANSWER B

REFERENCE:

PINGP 1576, pgs. 4 & 7 NEW HIGHER K/A: 2.4.41: Emergency Procedures / Plan: Knowledge of the emergency action level thresholds and classifications.

JUSTIFICATION:

a. Incorrect. Plausible as conditions are met for NUE; however, ALERT is the highest classification.

b. Correct.

c. Incorrect. Plausible as SAE conditions are met for the HOT tables of EAL matrix; however, in this case COLD tables apply and ALERT is highest classification.

d. Incorrect. Plausible as GE conditions are met for the HOT tables of EAL matrix; however, in this case COLD tables apply and ALERT is highest classification.

Proposed references to be provided to applicants during examination: PINGP 1576 Learning Objective: P7410L-002 Obj 3