ML15169A654

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Draft Written Exam (Folder 2)
ML15169A654
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 02/19/2015
From: Kelly M
Exelon Generation Co
To: Peter Presby
Operations Branch I
Shared Package
ML14254A311 List:
References
TAC U01911
Download: ML15169A654 (218)
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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 1 ID: 1118606 Points: 1.00 Unit 2 is at 85% power with the following conditions:

  • Feedwater master level control is in AUTOMATIC
  • Feedwater mode select is in "3-Element Control" and in AUTOMATIC
  • RPV level on narrow range Ll-2-06-094A is 19 inches
  • RPV level on narrow range Ll-2-06-094B is 27 inches
  • RPV level on narrow range Ll-2-06-094C is 25 inches Based on the above conditions the __(1L section of the "3-Element Control" will cause reactor feedpump speed to ___(2)_.

A. ( 1) L (2) rise B. ( 1) L (2) lower C. ( 1) S/F (2) rise D. ( 1) S/F (2) lower Answer: B Answer Explanation Choice Basis or Justification Correct: B Since steam flow equals feedwater flow, the L (Level) section of the 3-Element Control will resond to the difference in actual RPV level to the setpoint of 23 inches.

Feedwater level in AUTOMATIC will control RPV level based on the median level signal of 25 inches. Feedwater control will send a signal for the feed pump speed to lower to drive RPV level down to the setpoint of 23 inches.

Distractors: A Since steam flow equals feedwater flow, the L (Level) section of the 3-Element Control will resond to the difference in actual RPV level to the setpoint of 23 inches.

Feedwater level in AUTOMATIC will control RPV level based on the median level signal of 25 inches. Feedwater control will send a signal for the feed pump speed to lower to drive RPV level down to the setpoint of 23 inches.Plausible if the candidate does not understand that the feedwter system takes the median RPV level signal to make adjustments to feedpump speed.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 c The Steam flow/Feed flow section of the feedwater system will not make the adjustment because steam flow equals feedwater flow. Plausible if the candidate does not understand the relationship between the L and S/F section of the feedwater control system. Feedwater control will send a signal for the feed pump speed to lower to drive RPV level down to the setpoint of 23 inches.Plausible if the candidate does not understand that the feedwter system takes the median RPV level signal to make adjustments to feedpump speed.

D The Steam flow/Feed flow section of the feedwater system will not make the adjustment because steam flow equals feedwater flow. Plausible if the candidate does not understand the relationship between the L and S/F section of the feedwater control system.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1118606 User-Defined ID:

Cross Reference Number: 259002K3.05 Topic: ILT -5006-5t-002 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: New Exam item Previous NRC Exam X Modified Bank Other Exam Bank IL T Exam Bank Reference(s): PLOT - 5006 Learning PLOT - 5006-5t-001 Objective:

KIA System: 259002 Reactor Water Importance:

level Control System RO/SRO 3.6/ 3.7 KIA Statement: K1 .05 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Reactor feedwater system REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 3 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 2 ID: 1097805 Points: 1.00 A small break LOCA has occurred on Unit 3. The following conditions exist:

  • Drywell Pressure is 10 psig and rising
  • Drywell Temperature is 250 degrees F and rising
  • RPV Level is -165 inches and lowering
  • RPV pressure is 750 psig and lowering

A. Start the 3A Core Spray pump.

B. Start the 3C Core Spray pump.

C. Start the 3A and 38 Core Spray pumps.

D. Start the 3A and 3C Core Spray pumps Answer: D Answer Explanation Choice Basis or Justification Correct: D ADS Logic requires the correct combination of Core Spray pumps to complete the logic for an initiation. (A or B and C or D). Starting the A and C Core Spray pumps completes this logic.

Distracters: A Starting only the 3A Core Spray pump does not complete the logic for an initiation of ADS. Plausible if the candidate confuses the ADS initiation logic requirement for Core Spray with RHR which only requires one RHR pump to be operating.

B Starting only the 3C Core Spray pump does not complete the logic for an initiation of ADS. Plausible if the candidate confuses the ADS initiation logic requirement for Core Spray with RHR which only requires one RHR pump to be operating.

c ADS Logic requires the correct combination of Core Spray pumps to complete the logic for an initiation. (A or B and C or D). Starting the A and B Core Spray pumps does not complete this logic. Plausible if the candidate does not remember the correct combination of pumps required for logic initiation.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1097805 User-Defined ID:

Cross Reference Number: 209001 K1 .05 Topic: ILT-5014-5e-001 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(7)

Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): PLOT-5014, PLOT-5001G, M-1-S-54 Learning PLOT - 5014-5e-001 Objective:

KIA System: 209001 - Low Pressure Importance:

Core Spray System RO/SRO 3.7/ 3.7 KIA Statement: K1 .05 Knowledge of the physical connection and/or cause-effect relationship between LOW PRESSURE CORE SPRAY SYSTEM and the following: Automatic depressurization system REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 3 ID: 994361 Points: 1.00 Unit 2 is in MODE 4.

  • The "B" Loop of RHR is lined up to cool the fuel pool per AO 10.3-2, "RHR System to Fuel Pool Cross-Connect Operation" using the 2D RHR pump
  • Annunciator 005-B1, E-42 BUS DIFFERENTIAL OR OVERCURRENT RELAYS, is flashing.

The E4 Diesel Generator auto starts and:

A. energizes the E42 Bus. Shutdown Cooling remains in service.

B. energizes the E42 Bus. Fuel Pool Cooling using 'B' RHR Loop remains in service.

C. does NOT energize the E42 Bus. Shutdown Cooling is lost.

D. does NOT energize the E42 Bus. Fuel Pool Cooling using the 'B' RHR Loop is lost.

Answer: D Answer Explanation Choice Basis or Justification Correct: D E4 Diesel will auto start on low E-42 bus voltage, but does not load onto the E-42 bus due to the bus fault condition. With E-42 bus de-energized the 2D RHR pump has no power and therefore RHR system assist with fuel pool cooling is lost.

Distractors: A E4 Diesel output breaker is locked out from closing due to the E-42 bus fault.

Plausible if the candidate does not understand that the Bus Differential Overcurrent is a bus lockout.

B E4 Diesel is locked out, and the 2D RHR Pump will trip of loss of E-42 bus power.

Plausible if the candidate does not understand that the Bus Differential Overcurrent is a bus lockout. Plausible if the candidate does not understand that E-42 bus is the power supply for the 2D RHR pump.

c 2A RHR Pump is powered from the E12 Bus. Shutdown cooling will not be lost.

Plausible if the candidate does not understand the power supplies to the RHR pumps.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994361 User-Defined ID:

Cross Reference Number: 233000K2.01 Topic: ILT-5010-2a-OO 1 Num Field 1: NRC 2015 Num Field 2: 0.00 Text Field:

Comments:

Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b )(8)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank X IL T Exam Bank Reference(s): AO 10.3-2; ARC 005 B-1 Learning PLOT-5010-2a Objective:

K/A System: 203000 RHR/LPCI: Importance:

Injection Mode RO/SRO 3.5/ 3.5 K/A Statement: K2.01 Knowledge of electrical power supplied to the following: Pumps REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 4 ID: 1119614 Points: 1.00 The E-42 bus becomes deenergized.

This results in power being lost to which one of the following cooling water valves?

A. M0-2-10-89A "A HPSW HX Outlet".

B. M0-2-10-898 "B HPSW HX Outlet".

C. M0-2-10-89C "C HPSW HX Outlet".

0. M0-2-10-890 "O HPSW HX Outlet".

Answer: 0 Answer Explanation Choice Basis or Justification Correct: 0 Loss of power to the E-42 bus will cause a loss of power to M0-2-10-890 "O HPSW HX Outlet". The valve is powered directly from Motor Control Center E424-W-A.

Oistractors A Plausible if the candidate does not recall the power supply to the HPSW pump discharge valve.

B Plausible if the candidate does not recall the power supply to the HPSW pump discharge valve.

c Plausible if the candidate does not recall the power supply to the HPSW pump discharge valve.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 Svstem ID: 1119614 User-Defined ID:

Cross Reference Number: 400000 K2.02 Topic: ILT-5032-2b-003 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(7)

Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): SO 10.1.D-2, COL 32.1.A-2 Learning PLOT-5023-2b Objective:

KIA System: 400000 Component Importance Cooling Water System RO/SRO 2.9/ 2.9 KIA Statement: Knowledge of electrical power supplies to the following: CCW valves REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 5 ID: 1097845 Points: 1.00 Unit 2 is experiencing an ATWS. The following conditions exit:

  • Both SLC continuity lights are lit
  • Reactor pressure is 1050 psig
  • 2A SLC pump discharge pressure is 1150 psig
  • 2B RWCU pump is in-service vessel to vessel Based on the above conditions, SLC is ~~~~~~~~-

A. injecting. Reactor power will drop below 3% in less than 5 minutes.

B. injecting. Reactor Water Cleanup must be isolated.

C. NOT injecting. The 2B SLC pump must be started.

D. NOT injecting because the Squib valves did not fire.

Answer: B Answer Explanation Choice Basis or Justification Correct: B The 2A SLC pump is injecting. SLC pump discharge pressure is slightly higher than Reactor pressure. The Squib continuity lights do not extinguish when the pump switch is taken to START. RWCU did not isolate as required when the SLC pump switch was taken to START due to a problem with the SLC START switch. Because of this SLC START switch malfunction the RWCU system must be manullay isolated to shutdown the reactor with SLC.

Distractors: A SLC is injecting, RWCU did not isolate therefore reactor power will not go from 100% to less than 3% power within 8 minutes as verified on the Peach Bottom simulator. Plausible if the candidate does not recognize that RWCU is in-service and should have isolated automatically when the SLC control switch was taken to Start.

c SLC is injecting there is not a reason to start the 2B SLC pump. Plausible if the candidate does not understand the indication of an injecting positive displacement pump.

D SLC is injecting the Squib continuity lights do not extinguish when the pump control switch is taken to Start. Plausible if the candidate does not understand the indication of an injecting positive displacement pump and the operation of the Squib valves.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1097845 User-Defined ID:

Cross Reference Number:

Topic: ILT- 5011-6a-001 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(6)

Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SO 11.1.B-3 Standby Liquid Control System Initiation, PLOT - 5011 Learning ILT-5011-6a Objective:

KIA System: 211000 Standby Liquid Importance:

Control System RO/SRO 4.3/ 4.4 KIA K3.01 Knowledge of the effect that a loss or Statement: malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on the following:

Ability to shutdown the reactor in certain conditions.

REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O 6 ID: 1097864 Points: 1.00 Unit 2 HPCI is injecting into the RPV following a Group I isolation.

The following conditions exist:

  • HPCI steam piping area temperature is 210 degrees F and rising
  • RPV level is -100 inches and rising slowly
  • Drywell pressure is 1 psig and steady
  • HPCI pump discharge flow on Fl-2-23-108 is 5000 gpm and steady Based on the above conditions, the HPCI PCIS Group IV i s o l a t i o n - - - - - - - - -

A. will occur when HPCI area temperature reaches the 250 degrees F.

B. will occur when RPV level rises above -48 inches.

C. has failed. Close valve M0-2-23-15 "HPCI Steam Isolation" ONLY.

D. has failed. Close valve M0-2-23-15 "HPCI Steam Isolation" and remove the valve electrical feed.

Answer: D Answer Explanation Choice Basis or Justification Correct: D HPCI should have isolated. The area temperature is above the isolation setpoint of 200 degrees F.

Distractors: A The isolation setpoint is 200 degrees F. Plausible if the candidate confuses the HPCI isolation setpoint with the Reactor Building Main Steam Line isolation setpoint.

B The initiation signal does not affect the isolation setpoint. Plausible if the candidate does not understand the relationship of the initiation logic and the isolation logic.

c M0-15 will not stay closed with the initiation signal present (~ -48 inches RPV level).

Plausible if the candidate does not under stand how the initiation signal affects the M0-15 valve logic.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 6 Info Question Tvpe: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficultv: 1.00 System ID: 1097864 User-Defined ID:

Cross Reference Number: 223002 K3.01 Topic: IL T-5007G-51-001 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference( s): GP-8.F PCIS Isolation - Groups IV and IV-B, COL GP-8.F-Groups IV, and IV-B Isolation, M-1-S-23, M-1-S-36 Learning PLOT-5007G.51 Objective:

KIA System: 223002 Primary Importance:

Containment Isolation RO/SRO System/Nuclear Steam 3.6/ 3.6 Supplv Shut-off KIA Statement: K3.12 Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on the following:

High Pressure Coolant Injection REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 7 ID: 1097970 Points: 1.00 Unit 2 is in an outage.

  • The E-22 bus is deenergized with the E-222 breaker open and the E-322 breaker open.
  • The E-222 breaker and the E-322 breaker control switches are in "Normal After Trip".
  • A Loss of Off-Site power occurs.

Based on the above conditions, the E-2 Diesel Generator will:

A. NOT start.

B. start and energize ONLY the E-22 bus.

C. start and energize ONLY the E-23 bus.

D. start and energize BOTH the E-22 bus and the E-23 bus.

Answer: C Answer Explanation Choice Basis or Justification Correct: c The E-22 bus is not setup for fast transfer because both supply breakers are in "normal after trip". When the loss of off-site power occurs the D/G will start and only load the E-23 bus.

Distractors: A The DIG will receive a start signal from the undervoltage on the E-23 bus.

B The E-22 bus can not load the bus is not setup for fast transfer.

D The E-22 bus can not load the bus is not setup for fast transfer.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficultv: 0.00 System ID: 1097970 User-Defined ID:

Cross Reference Number: 264000K4.08 Topic: ILT-5052-3h-001 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 10CRF55.41(b)(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference( s): PLOT-5052 Learning PLOT-5052-3h Objective:

KIA System: 264000 Emergency Importance:

Generators RO/SRO 3.8 I 3.7 KIA Statement: K4.08 Knowledge of EMERGENCY GENERATORS design feature(s) and/or interlocks which provide for the following:

Automatic startup REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 15of164 21January2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 8 ID: 993543 Points: 1.00 Consider the following accident scenario:

T=O sec Small line break LOCA occurs.

T=10 sec RPV level is 1 inch, Reactor Scram occurs, and all Control Rods insert to full-in.

T=25 sec RPV level is -48 inches and dropping, HPCI and RCIC fail to start.

T=130 sec RPV level is -160 inches; MSIVs are shut, Low Pressure ECCS Pumps are running on minimum flow and all four Emergency Diesel Generators are running.

T=155 sec Drywell pressure is 2 psig and rising.

T=200 sec RCIC is manually started and is injecting into the RPV.

T=210 sec RPV level is steady at -130 inches.

Based on the above conditions, assuming no further operator action and no additional equipment malfunctions, the ADS system will - - - - - - - - -

A. NOT initiate.

B. initiate 105 seconds after T=155 seconds.

C. initiate 105 seconds after T=130 seconds.

D. initiate 9 minutes and 105 seconds after T=155 seconds.

Answer: A Answer Explanation Choice Basis or Justification Correct: A RPV level is recovered above -160 inches before the 105 second timer has timed out. This resets the ADS timer and a blowdown does not occur.

Distractors: B Plausible if the candidate does not understand that if RPV level is recovered above -

160 inches the logic resets.

c Plausible if the candidate does not understand that if RPV level is recovered above -

160 inches the logic resets. Plausible if the candidate does not remember that the logic needs either the 2 psig drywell signal or be below -160 inches for 9 minutes.

D Plausible if the candidate does not understand that if RPV level is recovered above -

160 inches the logic resets.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 993543 User-Defined ID:

Cross Reference Number: 218000K4.01 Topic: ILT-5001 G-3a-OO 1 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b )(8)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank X IL T Exam Bank Reference(s): M-1-S-52, PLOT-5001G Learning PLOT-5001G-3a Objective:

KIA System: 218000 Automatic Importance Depressurization System RO/SRO 3.7/ 3.9 KIA Statement: K4.01 Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which provide for the following: Prevent inadvertant initiation of ADS logic REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 9 ID: 1098003 Points: 1.00 Unit 3 is at power following a maintenance outage.

The following conditions exist:

  • Reactor power is 90% and steady
  • Total drive flow is 70% and steady Bases on the above conditions, a Simulated Thermal Power (STP) flow biased rod block will first occur at approximately (1) , and an STP flow biased scram will first occur at approximately (2)

A. (1) 90.6%

(2) 102.6%

B. (1) 100.0%

(2) 109.2%

C. (1) 108.0%

(2) 117.6%

D. (1)112.5%

(2) 121.7%

Answer: B Answer Explanation Choice Basis or Justification Correct: B .65(70)+54.5 =100.0% is the APRM rod block setpoint based on TRM values.

.65(70)+63.7 =109.2% for the APRM scram setpoint based on Tech Spec values.

Distractors: A These values were derived using an old calculation (.58w+62) for the scram setpoint and (.58w+50) for the rod block setpoint. Plausible if the candidate does not remember the correct formula for the setpoints.

c These are the clamped values for the Rod Block and the Scram. Plausible if the candidate does not recall the calculation and only the clamp values.

D These values were derived substituting 90% for the flow value. Plausible if the candidate is unsure of which value gets substituted for "W" in the calculation and uses the power value instead of flow.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1098003 User-Defined ID:

Cross Reference Number: 215005K5.05 Topic: IL T-5060-4e-001 Num Field 1:

Num Field 2:

Text Field:

Comments:

Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(6)

Source Documentation Source: New Exam item Previous NRC Exam X Modified Bank Other Exam Bank ILT Exam Bank Reference(s): Unit 3 Tech Spec Table 3.3.1.1-1, TRM Table 3.2-1 Learning PLOT-5060-4e Objective:

K/A System: 215005 Average Power Importance:

Range/Local Power RO/SRO Range Monitor System 3.6/ 3.6 K/A K5.05 Knowledge of the operational implications Statement: of the following concepts as they apply to AVERAGE POWER RANGE/LOCAL POWER RANGE MONITOR SYSTEM: Core flow effects on APRM trip setpoints REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 10 ID: 1098004 Points: 1.00 To parallel an Emergency Diesel Generator with a startup source that is supplying a 4kV bus, the Diesel Generator speed control must be in (1) and the Diesel must be running slow in the (2)

A. (1)droop (2) fast direction B. (1) droop (2) slow direction C. ( 1) isochronous (2) fast direction D. (1) isochronous (2) slow direction Answer: A Answer Explanation Choice Basis or Justification Correct: A When paralleling an Emergency Diesel Generator (EDG) with a startup source the EDG speed control must be in droop to allow for load sharing with the startup source. If the EDG speed control was in isochronous the EDG would try and pickup the load of the startup source (essentially the electric grid) and the EDG would run until it trips on an overload condition.

The EDG speed must be slow in the fast direction in order to ensure that the EDG picks up the bus load and does not trip on reverse power.

Distractors: B Incorrect. Correct speed control setting, however the running direction is not correct.

It must be slow in the FAST direction. Plausible if the candidate confuses EDG required speed direction if the EDG is already carrying the bus load and then wants to parallel with the off-site source.

c lncorrrect. The speed control setting of isochronous is not correct. Plausible if the candidate confuses EDG required speed control for carrying the bus alone (no startup source parrallel operations). The speed direction is correct.

D lncorrrect. The speed control setting of isochronous is not correct. Plausible if the candidate confuses EDG required speed control for carrying the bus alone (no startup source parrallel operations). Speed direction is only correct if the EDG is already carrying the bus load and then wants to parallel with the off-site source. Not the case here.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1098004 User-Defined ID:

Cross Reference Number: 262001 K5.01 Topic: IL T-5054-4a-001 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(7)

Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SO 52A 1. B Diesel Generator Operations Learning PLOT-5054-4a Objective:

KIA System: 262001 AC. Electrical Importance:

Distribution RO/SRO 3.1/3.7 KIA Statement: K5.01 Knowledge of the operational implications of the following concepts as they apply to AC.

ELECTRICAL DISTRIBUTION: Principle involved with paralleling two AC. sources REQUIRED None MATERIALS:

Notes and None Comments:

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 11 ID: 993231 Points: 1.00 Which one of the following identifies the available indications of reactor power in the Main Control Room during a loss of RPS "A" and "B" power on Unit 2?

Indication Location A APRM only 20C037 only B. WRNM only 20C036 only C. APRM only 20C005 and 20C037 D. WRNM only 20C005 and 20C036 Answer: D Answer Explanation I Choice Basis or Justification Correct: D The WRNM system does not receive any power from RPS, therefore a loss of RPS will not affect the WRNM indications or functions. WRNM displays on both the 20C005 and the 20C036 panels will remain available. A and B RPS busses supply all inputs to the Quad Low Voltage Power Supplies for all 4 of the APRMs. If both channels of RPS were lost, all four 2-out-of-4 logic modules and all four ARPM channels would lose power.

Distractors: A Incorrect. A and B RPS busses supply all inputs to the Quad Low Voltage Power Supplies for all 4 of the APRMs. If both channels of RPS were lost, all four 2-out-of-4 logic modules and all four ARPM channels would lose power. Also, the location is not correct. Panel 20C036 is where the WRNM moduled are located, not the APRM module.

B Incorrect. WRNM displays on both the 20C005 and the 20C036 panels will remain available.

c Incorrect. A and B RPS busses supply all inputs to the Quad Low Voltage Power Supplies for all 4 of the APRMs. If both channels of RPS were lost, all four 2-out-of-4 logic modules and all four ARPM channels would lose power.

PBS ILT 2015 CERT/NRC EXAM Page: 22 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 993231 User-Defined ID: IL T-5060C-3B-002 Cross Reference Number: 215003 K6.01 Topic: ILT-5060C-6b-002 Loss of Power to ODAs/Recorders Num Field 1: 2015 NRC Num Field 2: N/A Text Field: A Comments:

Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(7)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference( s): PLOT 5060C Learning PLOT 5060C-6b Objective:

KIA System: 215003 Intermediate Importance:

Range Monitors (IRM) RO/SRO System 3.8/ 3.8 KIA Statement: K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM: Reactor protection system (power supply)

REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 23 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 12 ID: 994536 Points: 1.00

  • A plant transient has resulted in a loss of power to 20Y034 and a subsequent failure of Unit 2 RPS to initiate a reactor scram.
  • Print M-1-S-46 sheets 1 and 2 are provided seperately for reference.

Based on the above conditons, which of the following describes the 2A SLC Pump response, including indications? The 2A SLC P u m p - - - - - - - - - - -

A. starts, both squib valves fire, running indication red light is lit, both squib valve continuity lights are lit.

B. starts, both squib valves fire, running indication red light is NOT lit, both squib valve continuity lights are NOT lit.

C. does NOT start, both squib valves do NOT fire, not running indication green light is lit, both squib valve continuity lights are lit.

D. does NOT start, both squib valves do NOT fire, the not running indication green light is NOT lit, both squib valve continuity lights are NOT lit.

Answer: B PBS ILT 2015 CERT/NRC EXAM Page: 24of164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Answer Explanation I Choice Basis or Justification Correct: B Standby Liquid Control (SLC) Pump, squib continuity and discharge manual valve position indication (HV-18) light indications are powered not from the pump breaker, but from 2(3)0Y34 Panel. Squib valve power comes from the SLC pump motor control center which is not affected by a loss of 20Y34.

Distractors: A Incorrect. A loss of 20Y34 causes loss of power to lights on COOSA. There would be no red running light indication nor any squib continuity lights lit under a loss of 20Y34.

c Incorrect. A loss of 20Y34 does not affect ability to start SLC. Pump power is from emergency related bus E-124-R-C. However, all related panel indicating lights are off.

D Incorrect. A loss of 20Y34 does not affect ability to start SLC. Pump power is from emergency related bus E-124-R-C PBS ILT 2015 CERT/NRC EXAM Page: 25 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994536 User-Defined ID:

Cross Reference Number: 211 OOOK6.03 Tooic: IL T-5011-?c-001 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments:

Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank X IL T Exam Bank Reference(s): M-1-S-46 Learning PLOT-5011.?c Objective:

KIA System: 211000 Standby Liquid Importance Control System RO/SRO 3.2/ 3.3 KIA Statement: K6.03 Knowledge of the effect that a loss or malfunction of the following will have on the STANDBY LIQUID CONTROL SYSTEM: AC.

Power REQUIRED Provide M-1-S-46, Sheets 1 and 2 to the MATERIALS: student Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 26 of 164 21January2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 13 ID: 1098022 Points: 1.00 A LOCA has occurred on Unit 2. The following conditions exist:

  • RPV level is -200 inches and steady
  • Drywell pressure is 7 psig and rising slowly
  • Core Spray flow as indicated on Fl-2-14-50B is 7000 gpm Based on the above conditions, reactor pressure is _ __,('"""1.,,_)_ , there ___(=2,_)_Adequate Core Cooling.

A (1) 300 psig (2) is B. (1) 300 psig (2) is not C. (1) 400 psig (2) is D. (1) 400 psig (2) is not Answer: A Answer Explanation Choice Basis or Justification Correct: A With injection RPV pressure must be less than the Core Spray discharge pressure of 330 psig. Core Spray flow is above the value for spray cooling with RPV level above -226 inches.

Distractors: B Plausible if the candidate does not recognize that ACC is established even with low level (above -226 inches) with adequate Steam Cooling.

c Plausible if the candidate does not understand the Core Spray discharge pressure with respect to Reactor pressure.

D Plausible if the candidate does not recognize that ACC is established even with low level (above -226 inches) with adequate Steam cooling. Plausible if the candidate does not understand the Core Spray discharge pressure with respect to Reactor pressure.

PBS ILT 2015 CERT/NRC EXAM Page: 27 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1098022 User-Defined ID:

Cross Reference Number: 209001A1 .04 Topic: ILT-5014-9k.4-001 Num Field 1: NRC 2015 Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): T-111, PLOT 5014 Learning PLOT-5014-9k.4 Objective:

K/A System: 209001 Low Pressure Importance Core Spray System RO/SRO 3.7/ 3.7 K/A Statement: A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including: Reactor pressure REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 28 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 14 ID: 1098332 Points: 1.00 Unit 3 was operating at 100% power with Torus temperature at 89°F A small break LOCA occurred and ADS has initiated.

Following the ADS blowdown the following conditions exist:

  • RPV level is 10 inches and rising
  • RPV pressure is 100 psig and lowering
  • Drywell pressure is 8 psig and lowering
  • Torus level is fluctuating between 14.65 feet and 14.85 feet Based on the above conditions, Torus temperature will be (1} the T-102 Torus temperature entry condition.

Long-term decay heat removal is ensured using a minimum of (2} RHR and HPSW pump(s).

A ( 1) less than (2) one B. ( 1) less than (2) two C. (1) greater than (2) one D. ( 1) greater than (2) two Answer: c PBS ILT 2015 CERT/NRC EXAM Page: 29 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer Explanation Choice Basis or Justification Correct: c An ADS blowdown will cause Torus temperature to rise above 95 degrees F which is the T-102 entry condition for high Torus temperature. One RHR pump with its associated HPSW pump is sufficient to handle decay heat load by design.

Distractors: A Incorrect. An ADS blowdown will cause Torus temperature to rise above 95 degrees F which is the T-102 entry condition for high Torus temperature. Plausible if the candidate does not recall that an ADS blowdown includes 5 open SRVs and a significant amount of energy to the Torus.

B Incorrect. An ADS blowdown will cause Torus temperature to rise above 95 degrees F which is the T-102 entry condition for high Torus temperature. One RHR pump with its associated HPSW pump is sufficient to handle decay heat load by design.

Plausible if the candidate does not remember these design conditions.

D Incorrect. One RHR pump with its associated HPSW pump is sufficient to handle decay heat load by design.

PBS ILT 2015 CERT/NRC EXAM Page: 30 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1098332 User-Defined ID:

Cross Reference Number: 218000A 1.06 Topic: ILT-5001 G-9k.6-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps* chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(5)

Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): T-102, PLOT-5001G Learning PLOT-5001 G-9k.6 Objective:

KIA System: 218000 Automatic Importance:

Depressurization System RO/SRO 4.1 /4.3 Kl A Statement: A 1.06 Ability to predict and/or monitor changes in parameter associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: Suppression pool temperature REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 31 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 15 ID: 1098361 Points: 1.00

  • A Station Blackout has occurred.
  • Unit 2 HPCI is injecting into the RPV to control RPV level.
  • A significant steam leak occurs just downstream of M0-2-23-16 "HPCI Steam Supply Isolation Valve" causing a HPCI isolation signal.

Based on the above conditions, choose the correct statement below regarding the HPCI system response and additional mitigating actions.

The HPCI steam leak will _ _ _ _ _ _ _ _ _ __

A automatically isolate. Bypass the high temperature isolation using SE-11 ATTACHMENT X, "Defeat of the HPCI and RCIC Steam Line High Temperature Isolation".

B. automatically isolate. Start RCIC using RRC 13.1-2, "RCIC System Operation During a Plant Event" to control RPV water level.

C. NOT automatically isolate. Isolate HPCI using GP-8.F "PCIS Isolation - Groups IV and IV-B" D. NOT automatically isolate. Trip HPCI using RRC 23.1-2, "HPCI System Operation During a Plant Event" to minimize the steam leak into the HPCI room.

Answer: B Answer Explanation Choice Basis or Justification Correct: B Even with a station blackout (SBO) HPCI will isolate M0-2-23-16 will close to isolate the leak since the logic and valve power is DC. When HPCI is out of Service RCIC will be the only system available to inject during a SBO event.

Distractors: A It is not appropriate to bypass the High temperature isolation with a steam leak. SE-11 Att X is only used to bypass the high temperature condition due to a lack of ventilation flow. Plausible if the candidate does not recall the purpose of SE-11 Att X.

c HPCI will isolate. GP-8 F is not required to perform the isolation because the isolation would have occurred. Plausible is the candidate does not recall that M0 23-16 is D.C. powered.

D HPCI will isolate. Tripping HPCI will not reduce the steam flow to the HPCI room.

Plausible is the candidate does not recall that M0-2-23-16 is D.C. powered.

Plausible if the candidate does not understand that the turbine trip will not minimize steam flow to the HPCI room.

PBS ILT 2015 CERT/NRG EXAM Page: 32 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1098361 User-Defined ID:

Cross Reference Number: 206000 A2.04 Topic: IL T-5023-?c-002 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference( s): PLOT 5023 Learning PLOT 5023-?c Objective:

KIA System: 206000 High Pressure Importance:

Coolant Injection System RO/SRO 2.7/ 3.0 KIA Statement: A2.04 Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: AC. failures REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 33 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 16 ID: 1098490 Points: 1.00 RCIC is aligned for injection following a Group I isolation. The following conditions exist:

  • RPV level is -100 inches and steady
  • RPV pressure is 1050 psig and steady
  • RCIC system flow is 60 gpm
  • RCIC turbine speed is 2600 rpm
  • The RCIC flow controller has failed to operate in automatic Based on the above conditions, choose the correct answer with respect to RCIC system operation and required operator action.

The RCIC system will _ _,,.(_,_1},__and the required operator action is to _ _,,.(=2,_}_

A (1) cause damage to the turbine exhaust check valve due to low RCIC RPMs (2) secure RCIC using SO 13.1-2, Section E, "RCIC System Shutdown".

B. ( 1) cause damage to the turbine exhaust check valve due to low RCIC RPMs (2) place the RCIC flow controller in manual and raise flow to 600 gpm using SO 13.1.C-2, "RCIC System Automatic Initiation Response".

C. (1) pump the Condensate Storage Tank to the Torus (2) secure RCIC using RRC 13.1-2, Section E, "RCIC System Shutdown".

D. (1) pump the Condensate Storage Tank to the Torus (2) place the RCIC flow controller in manual and raise flow to 600 gpm using SO 13.1.C-2, "RCIC System Automatic Initiation Response".

Answer: D Answer Explanation Choice Basis or Justification Correct: D With the low system flow condition of only 60 gpm the RCIC system will pump the CST through the open minflow valve to the Torus. RPV level is below the -48 inch automatic initiation setpoint SO 13.1.C directs that RCIC not be secured until RPV level is returned to the normal band.

Distractors: A With high Reactor pressure RCIC speed will not be low even though system flow is low. RCIC must remain in-service with low RPV level. Plausible if the candidate does not understand the relationship between RPV pressure and system speed.

Plausible if the candidate does not understand that securing RCIC would violate SO 13.1.C.

PBS ILT 2015 CERT/NRC EXAM Page: 34 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 B With high Reactor pressure RCIC speed will not be low even though system flow is low. Plausible if the candidate does not understand the relationship between RPV pressure and system speed.

c RCIC must remain in-service with low RPV level. Plausible if the candidate does not understand that securing RCIC would violate SO 13.1. C.

Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1098490 User-Defined ID:

Cross Reference Number: 217000 A2.10 Topic: IL T-5013-7e-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b )(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SO 13.1.C, PLOT 5013, ARC 222 B-1 Learning PLOT 5013.7e Objective:

KIA System: 217000 Reactor Core Importance:

Isolation Cooling System RO/SRO 3.1/3.1 KIA Statement: A2.10 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine control system failure REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 35 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRG Reactor Operator Exam - Revision 0 17 ID: 993215 Points: 1.00

  • A transient and plant trip from 100% power occurred on Unit 2.
  • Reactor pressure was observed to reach 1150 psig.

Based on the above conditions, _ _ _ _ _ _ _ should have opened to limit RPV pressure.

A Four (4) SRVs B. Eight (8) SRVs C. Eleven (11) SRVs D. All SRVs and the Safety Valves Answer: B Answer Explanation Choice Basis or Justification Correct: B As required by Technical Specifications, SRV lift setpoints are: 4 SRVs at 1135 psig, 4 SRVs at 1145psig, 3 SRVs at 1155 psig, and 3 Safety Valves at 1260 psig.

With a pressure of 1150 eight SRVs will have opened.

Distractors: A Plausible if the candidate does not recall the SRV lift points.

c Plausible if the candidate does not recall the SRV lift points.

D Plausible if the candidate does not recall the SRV and SV lift points.

PBS ILT 2015 CERT/NRG EXAM Page: 36 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 993215 User-Defined ID:

Cross Reference Number: 239002 A3.02 Topic: ILT -5001 A-3d-002 Num Field 1: 2015 NRC Num Field 2: N/A Text Field: A Comments:

Ps 1 chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(3)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): PBAPS Tech Specs 3.4.3, PLOT 5001A Learning PLOT-5001A-3d Objective:

KIA System: 239002 Relief/Safety Importance:

Valves RO/SRO 4.3/ 4.3 KIA Statement: A3.02 - Ability to monitor automatic operations of the RELIEF/SAFETY VALVES including:

SRV operation on high reactor pressure REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 37 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 18 ID: 1118556 Points: 1.00 A transient has resulted in the following conditions on Unit 3:

  • RPV level has lowered to -60 inches
  • All automatic initiations and isolations have occurred as required
  • NO operator actions have been performed Based on the above conditions, select the status of the Standby Gas Treatment (SBGT) System fans and filter train status.

Standby Gas Treatment Fans ___(~1),.__started and the dampers for the ___(=2),.__ SBGT Filter Train(s) is/are open.

A. (1) Band C (2) B only B. (1) A and C (2) A and B C. (1) Band C (2) A and B D. (1) A, B, and C (2) A and B Answer: c Answer Explanation Choice Basis or Justification Correct: c A Group Ill PCIS isolation has occurred due to reactor level being less than +1 inch. Since the transient occurred on Unit 3 the Band C SBGT fans will automatically start and both the A and B SBGT filter trains will align for service.

Distractors: A Incorrect. Both the A and B SBGT filter trains will align for service, not just the B train. Plausible if the candidate thinks that only the B filter train lines up for Unit 3 only.

B Incorrect. The A SBGT fan will only start on a Group Ill isolation signal on Unit 2. Not the case here.

D Incorrect. Plausible based on that all three SBGT fans start with both filter trains align if a dual-unit transient occurs. This event is on Unit 3 only.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1118556 User-Defined ID: ILT-5009A-4A-001 Cross Reference Number: 288000 K4.03 Topic: ILT-5009A-4a-002 Rx Lo Lo Level I status of vent and sbqt Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(9)

Source Documentation Source: LJ New Exam Item LJ Previous NRC Exam:

D Modified Bank D Other Exam Bank:

Item 1ZJ ILT Exam Bank Reference(s): GP-8.B; GP-8.B COL Learning PLOT-5009a-3a Objective:

KIA System: 261000 - Standby Gas Importance:

Treatment System RO/SRO 3.0 I 2.9 KlA Statement: A3.03 -Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Valve operation REQUIRED NONE MATERIALS:

Notes and Comments:

PBS IL T 2015 CERT/NRC EXAM Page: 39 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 19 ID: 1102305 Points: 1.00 During performance of GP-11.E, "Reactor Protection System - Scram and ARI Reset" the URO takes the "Scram Reset" switch in the Group 1 and 4 position.

With respect to the four (4) white scram group light on the RPS panels (C015 and C017), this action will cause _ _ _ _ __

A. four (4) white scram group lights to light on the C015 panel ONLY B. four (4) white scram group lights to light on the C017 panel ONLY C. two (2) white scram group lights to light on BOTH C015 and C017 panels D. no change in indication until the "Scram Reset" switch is taken to position Group 2 and 3.

Answer: C Answer Explanation Choice Basis or Justification Correct: c When the scram reset switch is taken to the position 1 and 4. It closes the scram inlet and outlet valves for two of the four rod groups. The white lights on both the C015 and C017 panels are indications of the rod group reset.

Distractors: A Plausible if the candidate does not understand how the scram reset logic functions.

The candidate could believe that turn the switch to position 1 and 4 resets the "A" logic causing all 4 lights on C015 to light.

B Plausible if the candidate does not understand how the scram reset logic functions.

The candidate could believe that turn the switch to position 1 and 4 resets the "B" logic causing all 4 lights on C017 to light.

D Plausible if the candidate does not understand how the scram reset logic functions.

GP-11. E for the scram reset does not have the operator check the lights until the scram reset switch is taken to position 1 and 4 then 2 and 3. At this point all for the white lights would be lit.

PBS ILT 2015 CERT/NRG EXAM Page: 40 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1102305 User-Defined ID:

Cross Reference Number: 212000 A4.14 Topic: ILT-5060F-9g-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(6)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): GP-11 E, M-1-S-54 Learning PLOT 5060F-9g Objective:

KIA System: 212000 Reactor Importance:

Protection System RO/SRO 3.8/ 3.8 KIA Statement: A4.14 Ability to manually operate and/or monitor in the control room: Reset system following system activation REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 41 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 20 ID: 1104746 Points: 1.00

  • A Reactor startup is in progress on Unit 2.
  • The start up has exceeded three doublings of the initial count rate.
  • A picture of a WRNM display is below.

Choose the correct statement with respect to the reactor startup.

Control rod withdraw c a n - - - - - - - - - - -

A continue. Use single notch withdraw.

B. continue. Use continuous withdraw.

C. NOT continue. Allow period to drop to 150 seconds before continuing to withdraw control rods.

D. NOT continue. Allow period to drop to 250 seconds before continuing to withdraw control rods.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer: D Answer Explanation Choice Basis or Justification Correct: D The indications on the WRNM indicate that the reactor is below the point of adding heat and Period is approximately 100 seconds. Per GP-2 while in this condition the operator must allow period to decay to 250 second before beginning to withdraw control rods.

Distractors: A Plausible if the candidate does not recall the requirement to allow period to decay or if the candidate cannot properly interpret the indications on the WRNM display.

B Plausible if the candidate does not recall the requirement to allow period to decay or if the candidate cannot properly interpret the indications on the WRNM display.

c Plausible if the candidate does not recall the value at which rod withdraw can begin again.

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EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104746 User-Defined ID:

Cross Reference Number: 215004A4.03 Topic: ILT5060C-9a-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps~ chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 10CRF55.41(b)(10)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): GP-2 Learning PLOT-5060C-9a Objective:

KIA System: 215004 Source Range Importance:

Monitor (SRM) System RO/SRO 2.9/ 2.7 KIA Statement: A4.03 - Ability to manually operate and/or monitor in the control room: CRT Displays:

Plant-Specific REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 44of164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 21 ID: 994785 Points: 1.00 Given the following:

  • A AIR COMP TROUBLE (216 8-1) alarm is received
  • The 'A' Air Compressor (2AK001) indicates "tripped" on Panel 20C012
  • Investigation shows the 'A' Air Compressor tripped on high receiver pressure
  • 'A' Instrument Air Receiver (2AT006) pressure is currently 105 psig Per ARC 216 B-1, which one of the following is correct regarding reset of the 'A' Air Compressor trip?

A. Air receiver pressure does NOT allow the air compressor trip to be reset.

B. Air receiver pressure allows the air compressor trip to automatically reset.

C. The trip can only reset by depressing the "Reset-Start" button locally at the compressor.

D. The trip can only be reset by placing the compressor control switch to STOP at Panel 20C012.

Answer: C Answer Explanation Correct: c Per ARC-216 B-1, a high receiver pressure trip occurs at 120 psig. Since normal system pressure is 100 to 115 psig, current receiver pressure (105 psig) allows compressor reset. Per the NOTE in ARC-216 B-1, a compressor trip can only be reset locally by depressing the "Reset-Start" button located at the tripped compressor.

Distractors: A Per ARC-216 B-1, a high receiver pressure trip occurs at 120 psig. Since normal system pressure is 100 to 115 psig, current receiver pressure (105 psig) allows compressor reset.

B Per the NOTE in ARC-216 B-1, a compressor trip can only be reset locally by depressing the "Reset-Start" button located at the tripped compressor.

D Per the NOTE in ARC-216 B-1, a compressor trip can only be reset locally by depressing the "Reset-Start" button located at the tripped compressor.

PBS ILT 2015 CERT/NRC EXAM Page: 45 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994785 User-Defined ID: IL T-5036-SC-OO 1 Cross Reference Number: 300000 2.4.31 ILT-5036-Sc-001 Given the following: *A AIR COMP TROUBLE (216 Topic:

B-1) alarm is received. *The 'A' Air Num Field 1: 2015 NRC Num Field 2:

Text Field: NRC-09-1 Comments: Ps ichometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): ARC-216 B-1 Learning PLOT-5036-Sc Objective:

KIA System: 300000 Instrument Air Importance:

System RO/SRO 4.2/ 4.1 KIA Statement: 2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 46 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 22 ID: 1119137 Points: 1.00 Per procedure SE-13, "Loss of a 125 or 250 VDC Safety Related Bus", loss of power to 125 VDC Distribution Panel 20D021 results in the (1} Diesel Generator being INOP due to a loss of (2}

logic.

A ( 1) E-1 (2) RHR B. ( 1) E-1 (2) Core Spray C. (1) E-2 (2) RHR D. (1) E-2 (2) Core Spray Answer: B Answer Explanation Correct: B Per SE-13, a loss of 20D021 results in the E-1 Diesel Generator being INOP due to a loss of Core Spray logic.

~---*

Distractors: A Plausible if the candidate does not understand that Diesel Generator logic is from Core Spray logic and not RHR logic.

c Plausible if the candidate confuses the 20D021 and 20D022 distribution panel loads.

D Plausible if the candidate confuses the 20D021 and 20D022 distribution panel loads. Plausible if the candidate does not understand that Diesel Generator logic is from Core Spray logic and not RHR logic PBS ILT 2015 CERT/NRC EXAM Page: 47 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1119137 User-Defined ID: ILT-5057-6B-002 Cross Reference Number: 263000 2.4.21 Topic: ILT-5057-6B-003 Num Field 1: 2015 NRC Num Field 2:

Text Field: NRC-09-1 Comments:

Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(8)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): SE-13 Learning PLOT 5057-6b Objective:

KIA System: 263000 D.C. Electrical Importance:

Distribution RO/SRO 4.0/ 4.6 KIA Statement: 2.4.21 - Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 48 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 23 ID: 1102784 Points: 1.00 The following conditions exist on Unit 3:

  • The Reactor is in Mode 5
  • LPRM string replacements are in progress
  • SO 10.1.C-3 "Residual Heat Removal System Precise Reactor Temperature Control" is in progress with the following lineup:
  • "C" HPSW pump is in service through the "C" RHR Heat Exchanger
  • HV-3-32-32228A, '"'ILRT HPSW Cooling Bypass Valve" is throttled to maintain RPV temperature
  • RHR flow is 6000 gpm
  • RPV temperature is 110 degrees F. and rising slowly P&IDs M-315 Sheet 3, and M-361 Sheet 3, are provided for reference.

Per SO 10.1.C-3, in order to lower RPV temperature the operator shall:

A. raise RHR flow to 7000 gpm.

B. start a second HPSW Pump.

C. throttle OPEN HV-3-32-32228A, "ILRT HPSW Cooling Bypass Valve".

D. throttle CLOSED HV-3-32-32228A, "ILRT HPSW Cooling Bypass Valve".

Answer: C PBS ILT 2015 CERT/NRC EXAM Page: 49 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer Explanation Choice Basis or Justification Correct: c SO 10.1.C-3 "Residual Heat Removal System Precise Reactor Temperature Control" directs that to adjust RPV temperature, throttle HV-3-32-22228A, '"'ILRT HPSW Cooling Bypass Valve" is throttled to maintain RPV temperature. HV-3 22228A, ""ILRT HPSW Cooling Bypass Valve" must be throttled open to provide more cooling to the "A" RHR heat exchanger.

Distractors: A SO 10.1. B-3 "Residual Heat Removal System Shutdown Cooling Mode Manual Start" has a caution "Do NOT exceed RHR flow rate of 6500 gpm IF in-core instrumentation is NOT supported by blade guides OR fuel bundles on all sides unless greater flow is required to maintain desired Reactor water temperature below Technical Specification limits. Since LPRM strings are being replaced flow can not be raised to 7000 gpm. Plausible if the candidate does not recall this caution.

B SO 32.1.A-3, "High Pressure Service Water System Startup and Normal Operations" has a caution "Throttling M0-3-10-089A, "HPSW Hx Outlet" with HPSW in-service in the associated loop, will result in damage to the valves due to high vibration." With the "A" RHR heat Exchanger pressurized this caution applies.

Plausible if the candidate does not recall this caution.

D Throttling closed HV-3-32-22228A, ""ILRT HPSW Cooling Bypass Valve" would reduce the flow to the "A" RHR heat exchanger and cause temperature to rise.

Plausible if the candidate does not understand the valve lineup required to maintain precise temperature control.

PBS ILT 2015 CERT/NRC EXAM Page: 50of164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1102784 User-Defined ID:

Cross Reference Number: 205000K5.03 Topic: ILT5010-4e-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps1 chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SO 10.1.C-3, "Residual Heat Removal System Precise Reactor Temperature Control", M-361, M-315, SO 10.1.B-3 "Residual Heat Removal System Shutdown Cooling Mode Manual Start",

SO 32.1.A-3, "High Pressure Service Water System Startup and Normal Operations" Learning PLOT 5010 4e Objective:

KIA System: 205000 Shutdown Importance:

Cooling System (RHR RO/SRO Shutdown Cooling 2.8/ 3.1 Mode)

KlA Statement: K5.03 - Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE: Heat removal mechanisms REQUIRED P&IDs M-361 Sheet 3, M-315 Sheet 3 MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 51 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 24 ID: 995190 Points: 1.00 The following conditions exist on Unit 2:

  • A reactor startup is in progress
  • Critical data has just been recorded
  • The "B" and "D" Wide Range Neutron Monitor (WRNM) channels trip INOP simultaneously The plant impact from the WRNM system will b e - - - - - - - - -

A. alarm ONLY; no rod blocks or scram signals B. alarm and rod block ONLY; no scram signals C. alarm, rod block, AND half scram ONLY D. alarm, rod block, AND full scram Answer: C Answer Explanation Choice Basis or Justification Correct: c INOP failure is a "trip" signal. One in each trip system will generate a full scram, the "High/INOP' annunciator, and a control rod block. WRNM "B" is RPS B. WRNM "D" is RPS B. INOP will result in Rod Block and Scram input. RPS Logic for WRNM is 1 out of 4 taken twice. Rod Block, RPS HALF-SCRAM, and Alarm logics are all satisfied.

Distractors: A INOP failure is a "trip" signal. One in each trip system will generate a full scram, the "High/INOP' annunciator, and a control rod block. Plausible if candidate does not equate INOP with ROD BLOCK function.

B INOP failure is a "trip" signal. One in each trip system will generate a full scram, the "High/INOP' annunciator, and a control rod block. Plausible if candidate does not equate INOP with TRIP function for RPS (HALF SCRAM since both WRNM Channels are RPS B).

D A full scram will result from a trip signal in each channel. Plausible if candidate does not recognize that WRNM "B" and "D" are in the same RPS channel.

PBS ILT 2015 CERT/NRC EXAM Page: 52of164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 995190 User-Defined ID: 13 CERT Cross Reference Number: 215004 K3.01 Topic: IL T 5060C-6a-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps* chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 10CFR55.41 (b)(6)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): ARC-210 J-2 Learning PLOT - 5060C-6a Objective:

KJA System: 215004 - Source Range Importance:

Monitor (SRM) System RO/SRO 3.4/ 3.4 KJA Statement: K3.01 - Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM) SYSTEM will have on the following: RPS REQUIRED NONE MATERIALS:

Notes and None Comments:

PBS IL T 2015 CERT/NRC EXAM Page: 53 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 25 ID: 1102869 Points: 1.00

  • Drywell pressure is 70 psig due to a LOCA on Unit 2.
  • Containment venting is in progress using the "A" Standby Gas Treatment (SBGT) filter train via the 18 inch Torus vent.

Based on the above conditions, what is the impact to the SBGT system efficiency and the required operator action as moisture reaches the filter train charcoal filter?

The "A" SBGT efficiency will (1) , the operator shall _...,.(=2,_)_

A. (1) lower (2) secure venting in accordance with T-200D-2, Containment Venting Via the Torus 18 Inch Vent to SBGT B. (1) lower (2) place the "B" SBGT filter train in service in accordance with SO 9A.1. B, Standby Gas Treatment System Manual Startup C. (1) be unaffected (2) continue to monitor Drywell pressure in accordance with T-102, Primary Containment Control D. (1) be unaffected (2) maximize SBGT flow by placing the "B" SBGT train in service in accordance with SO 9A.1.B, Standby Gas Treatment System Manual Startup Answer: B Answer Explanation Choice Basis or Justification Correct: B The SBGT Design Basis Document states that SBGT efficiency will drop if the charcoal is wet. T-200 directs the operator to remove one SBGT Filter from service before venting begins. This is to maintain the other train for future use. With the Drywell pressure above the vent pressure the "B" SBGT filter needs to be placed in service so does rates can be minimized as venting continues.

Distractors: A Drywell pressure is still above the pressure required for venting. There for securing the vent lineup would not be the correct action to take. Plausible if the candidate does not recall the required vent pressure.

c The SBGT Design Basis Document states that SBGT efficiency will drop if the charcoal is wet. Plausible if the candidate does not understand how SBGT Charcoal functions to remove radionuclides.

D The SBGT Design Basis Document states that SBGT efficiency will drop if the charcoal is wet. If the "A" SBGT filter was efficient, T-200 would require that the "B" SBGT filter remain out of service. Plausible if the candidate does not understand how SBGT Charcoal functions to remove radionuclides. Plausible if the candidate does not recall the purpose of keeping the second SBGT filter train out of service.

PBS ILT 2015 CERT/NRC EXAM Page: 54 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1102869 User-Defined ID:

Cross Reference Number: 261 OOOA2-04 Topic: ILT5009A-1 Oc-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowanc e

(minutes)

HIGH 1OCRF55.41 (b)(13)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SBGT DBD, T-200 Learning PLOT 50009A-1 Oc Objective:

KIA System: 261000 Standby Gas Importance:

Treatment System RO/SRO 2.5/ 2.7 KIA Statement: A2.04 - Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High train moisture content REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 55 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 26 ID: 1102905 Points: 1.00 In accordance with procedure T-102, "Primary Containment Control", when RCIC suction is aligned to the Torus, RCIC must be secured when Torus level reaches (1) in order to prevent (2)

A. (1)6ft (2) loss of NPSH due to vortexing B. (1)6ft (2) over pressurizing the Torus due to uncovering the RCIC exhaust line C. (1)9.5ft (2) loss of NPSH due to vortexing D. (1)9.5ft (2) over pressurizing the Torus due to uncovering the RCIC exhaust line Answer: A Answer Explanation Choice Basis or Justification Correct: A T-102, "Primary Containment Control" states that RCIC is secured when Torus level reaches 6 ft due to vortexing.

Distractors: B T-102 requires HPCI to be removed from service due to pressurizing containment.

Plausible if the candidate confuses the reason for securing HPCI with RCIC.

c Plausible if the candidate confuses the level to secure RCIC with the level to secure HPCI.

D Plausible if the candidate confuses the level to secure RCIC with the level to secure HPCI. Plausible if the candidate confuses the reason for securing HPCI with RCIC.

PBS ILT 2015 CERT/NRG EXAM Page: 56 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 26 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1102905 User-Defined ID:

Cross Reference Number: 217000K1 .03 Topic: ILT-5013-5c-006 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psuchometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(8)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): T-102 Learning PLOT 5013-5c Objective:

KIA System: 217000 Reactor Core Importance Isolation Cooling System RO/SRO (RCIC) 3.6/ 3.6 KIA Statement: K1 .03 Knowledge of the physical connections and/or cause-effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following:

Suppression pool REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 57of164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 27 ID: 1102977 Points: 1.00 A Reactor startup is in-progress on Unit 3.

  • Reactor Power is 50%.
  • Rod 02-27 is selected and is to be withdrawn to position 48.

A core map is provided below for reference.

,--......--1-****** .

=:[i-9~_-:1,_-=-~--=-:_-=--+-+---+1--1-r!~=

u ....... ,~

I

. ~

' I

  • ~ '

J~  ;

--+---+--<----******'*.,*~<< . ~-r--..._---;--+---+-+--+----1

}I

-+---i--!-1 I

---+---~-~

r!**

2.1 II II  ! I j 19

'----+-_,._ _,___ _ .. 4 ..~

-~-+--t--1---+---!-~ H 1,

I :_,j i 11 ..

I --+--;--,-

(fl 00 i

00 10

-====,UJJ

+{..........._,1.-Jl___._-.-J-,

~ 41!: ~ ~ ~I For the above conditions, select the correct statement below with respect to the Rod Block Monitor (RBM) response.

The RBM will _ _ _ _ __

A. NOT initiate a rod block on rod 02-27 as local power rises.

B. initiate a rod block on rod 02-27 when local power rises to 114%.

C. initiate a rod block on rod 02-27 when local power rises to 119%.

D. initiate a rod block on rod 02-27 when local power rises to 124%.

Answer: A PBS ILT 2015 CERT/NRC EXAM Page: 58 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer Explanation Choice Basis or Justification Correct: A The RBM is bypassed when an edge rod is selected. Rod 02-27 is an edge rod.

The rod block monitor will not initiate rod blocks.

Distractors: B Plausible if the candidate does not recall that the RBM is bypassed when an edge rod is selected. The setpoint of 114% is the RBM High Trip Setpoint (HTSP) for Unit 3. The Low Trip Setpoint (L TSP) is the applicable RBM setpoint at 50% reactor power.

c Plausible if the candidate does not recall that the RBM is bypassed when an edge rod is selected. The setpoint of 119% is the RBM Intermediate Trip Setpoint (ITSP) for Unit 3. The Low Trip Setpoint (L TSP) is the applicable RBM setpoint at 50%

reactor power.

D Plausible if the candidate does not recall that the RBM is bypassed when an edge rod is selected. The setpoint of 124% is the RBM LTSP for Unit 3. The Low Trip Setpoint (L TSP) is the applicable RBM setpoint at 50% reactor power.

PBS ILT 2015 CERT/NRC EXAM Page: 59 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 27 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1102977 User-Defined ID:

Cross Reference Number: 215002K1 .06 Topic: ILT-5060-5h-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps 1 chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(6)

Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): PLOT-5060, ARC-311 C3, COLR Section 6.0 Learning PLOT-5060-5h Objective:

KIA System: 215000 Rod Block Importance:

Monitor System RO/SRO 3.0 I 3.1 KIA Statement: K1 .06 - Knowledge of the physical connections and/or cause-effect relationships between ROD BLOCK MONITOR SYSTEM and the following:

Control rod selection REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 60 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 28 ID: 1103318 Points: 1.00 A loss of power to the "B" RPS bus will cause a loss of power to which of the Main Steam Line Radiation Monitors listed below?

A A and B B. A and C C. Band D D. C and D Answer: C Answer Explanation Choice Basis or Justification Correct: c B RPS supplies power to the "B" and "D" radiation monitors.

Dis tractors: A Plausible if the candidate does not remember the RPS power supply logic and confuses it with other rad monitor logic that is "A" and "B" for trips.

B Plausible if the candidate does not remember the RPS power supply logic and confuses it with the "A" RPS power supply.

D Plausible if the candidate does not remember the RPS power supply logic and confuses it with other rad monitor logic that is "C" and "D" for trips.

PBS ILT 2015 CERT/NRC EXAM Page: 61 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 28 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1103318 User-Defined ID:

Cross Reference Number: 272000K2.01 Topic: IL T-5063-2a-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psvchometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): M-1-S-54, PLOT-5063 Learning PLOT-5063-2a Objective:

KIA System: 272000 Radiation Importance:

Monitoring System RO/SRO 2.5/ 2.8 KIA Statement: K2.01- Knowledge of electrical supplies to the following: Main steamline radiation monitors REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 62 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 29 ID: 1103404 Points: 1.00 Unit 2 is operating at 70% power with a reactor startup in progress. The following conditions exist:

  • "A" and "B" Condensate pumps are in-service
  • "B" and "C" Reactor feed pumps are in-service
  • RPV level is at 23 inches being controlled in automatic
  • "A" Steam packing exhauster is in-service
  • M0-2-05-2104A and M0-2-05-2105A, "A" SPE/SJAE Isolation Valves fail closed due to a malfunction Based on the above conditions, what is ( 1) the plant impact, if any, and (2) the required Operator response?

A. (1) no impact (2) continue with the startup B. (1) lowering main condenser vacuum (2) place the "B" SJAE in-service C. (1) loss of feedwater flow (2) place the Mode Switch in Shutdown D. (1) rising Main Stack radiation levels (2) place the "B" SPE in-service Answer: B Answer Explanation Choice Basis or Justification Correct: B The SPE/SJAE isolation valves are interlocked with the steam isolation valve for the SJAE. When M0-2104NM0-2105A fail closed they cause an isolation of the "A" SJAE. This will cause a loss of vacuum because non-condensible gasses are no longer being removed. Normal operation is for the M0-2104B/M0-2105B to be open. This facilitates placing the "B" SJAE in service. Placing the "B" SJAE in-service will stop the vacuum drop.

Distractors: A The SPE/SJAE isolation valves are interlocked with the steam isolation valve for the SJAE. When M0-2104NM0-2105A fail closed they cause an isolation of the "A" SJAE. This will cause a loss of vacuum because non-condensible gasses are no longer being removed. Plausible if the candidate forgets the interlock between MO-2104/M0-2105 and SJAE.

PBS ILT 2015 CERT/NRC EXAM Page: 63 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O c Since M0-2104B and 2105B are normally open there is not a loss of feedwater flow to the RPV. Plausible if the candidate does not recall that M0-2104B and 2105B are normally open. If a complete loss of feedwater had occurred then placing the Mode Switch in shutdown would be an appropriate action.

D When M0-2104A and M0-2105A close the "A" SPE would isolate. This would make Main Stack radiation levels drop not rise. Plausible is the candidate does not understand the operation of the SPE. Since the "A" SPE will isolate place the "B" SPE would be a correct action.

Question 29 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1103404 User-Defined ID:

Cross Reference Number: 256000K3.08 Topic: IL T-5005-6e-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps vchometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 10CRF55.41 (b )(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): M-307, PLOT 5005 Learning PLOT 5005-6e Objective:

KIA System: 256000 Reactor Importance:

Condensate System RO/SRO 2.8/ 2.8 KIA Statement: K3.08 - Knowledge of the effect that a loss or malfunction of the REACTOR CONDENSATE SYSTEM will have on the following: SJAE REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 64 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 30 ID: 993375 Points: 1.00 Which one of the following identifies the design function of the vacuum breakers that connect the Secondary Containment to the Primary Containment?

Vacuum breakers open to prevent. .....

A high Reactor Building pressures from actuating the Reactor Building blowout panels.

B. low Reactor Building pressures from actuating the Reactor Building blowout panels.

C. high Primary Containment pressures from exceeding Primary Containment design limits.

D. low Primary Containment pressures from exceeding Primary Containment design limits.

Answer: D Answer Explanation Basis or Justification Choice Correct: D Vacuum breakers open on high Reactor Building (RB) to Torus DP to limit Primary Containment (PC) pressure drop that could exceed the negative PC design pressure.

Distractors: A Plausible if the candidate does not understand the purpose of the vacuum breakers and believe the vacuum breakers open on high RB pressure vs low containment pressure.

B Plausible if the candidate does not understand the purpose of the vacuum breakers and believe the vacuum breakers open on low RB pressure vs low containment pressure.

c Plausible if the candidate does not understand the purpose of the vacuum breakers and believe the vacuum breakers open on high containment pressure RB pressure vs low containment pressure.

PBS ILT 2015 CERT/NRC EXAM Page: 65 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 30 Info Question Tvoe: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficultv: 0.00 Svstem ID: 993375 User-Defined ID: IL T-5009-4A-OO 1 Cross Reference Number: 290001K5.01 Topic: IL T-5009-3a-001 Desiqn function of Vacuum Breakers Num Field 1: 2015 NRC Num Field 2: N/A Text Field: A Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b )(9)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): PLOT 5009 Learning PLOT-5009-3a Objective:

KIA System: 290001 Secondary Importance:

Containment RO/SRO 3.3/ 3.4 KIA Statement: K5.01- Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT: Vacuum breaker operation REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 66 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O 31 ID: 1104771 Points: 1.00 During a Radwaste Floor Drain Sample Tank release to the Conowingo Pond per station procedures, the following Control Room alarms come in:

  • RADWASTE DISCH HI RADIATION (218 B-2)
  • RADWASTE DISCHARGE TO CANAL INTERLOCK TRIP (216 L-3)

Based on the above alarm conditions the release will automatically isolate (1)

The radiation units associated with this realease are measured in (2)

A. (1) immediately (2) mRem B. (1) immediately (2) counts/second C. ( 1) after a time delay (2) mRem D. (1) after a time delay (2) counts/second Answer: B Answer Explanation Choice Basis or Justification Correct: B High dose rate isolates with no time delay. The dose rate is calculated in counts per second as determined by procedures ST-C-095-805-2 "Liquid Radwaste Discharge".

Distractors: A The isolation occurs bases on dose rate not on dose. Plausible if the candidate confuses or does not understand the difference between dose and dose rate.

c There is no time delay. Plausible if the candidate does not understand the Radwaste isolation logic. The isolation occurs bases on dose rate not on dose.

Plausible if the candidate confuses or does not understand the difference between dose and dose rate.

D There is no time delay. Plausible if the candidate does not understand the Radwaste isolation logic.

PBS ILT 2015 CERT/NRG EXAM Page: 67 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 31 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104771 User-Defined ID:

Cross Reference Number: 268000K501 Topic: IL T-5020-4a-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficult Time RO Knowledge y Allowance (minutes)

HIGH 1OCRF55.41 (b)(13)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): PLOT-5063, ARC-218 B-2, ARC 216 L-3, ST-C-095-805-2 Learning PLOT-5020-3a Objective:

KIA System: 268000 Radwaste Importance:

RO/SRO 2.7/ 3.0 KIA K5.01 - Knowledge of the operational implications Statement: of the following concepts as they apply to RADWASTE: Units of radiation, dose, and dose rate REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 68 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 32 ID: 1119138 Points: 1.00 Unit 3 is operating at 50% power when a sustained loss of Instrument Air occurs.

A loss of Instrument Air header pressure causes the --'(__,__1),__Main Steam Isolation Valves close.

This will result in a (2) scram.

A (1) inboard (2) half B. (1) inboard (2) full C. ( 1) outboard (2) half D. (1) outboard (2) full Answer: D Answer Explanation Choice Basis or Justification Correct: D The outboard Main Steam Isolation Valves (MSIVs) do not have accumulators to hold the valves open. As Instrument Air pressure lowers the MSIVs will close. 3 of the 4 MSIV lines closing will generate a full scram signal.

Dis tractors: A Inboard MSIVs use Instrument Nitrogen as the motive force. Inboard MSIVs also have accumulators that will both hold the MSIVs open and provide the force to rapidly close the MSIVs. Plausible if the candidate does not recall the motive force for the inboard MS IVs and is not familiar with the arrangement of the accumulator.

Plausible if the candidate is not familiar with the RPS logic for MSIV closure.

B Inboard MSIVs use Instrument Nitrogen as the motive force. Inboard MSIVs also have accumulators that will both hold the MS IVs open and provide the force to rapidly close the MSIVs. Plausible if the candidate does not recall the motive force for the inboard MS IVs.

c Plausible if the candidate is not familiar with the RPS logic for MSIV closure.

PBS ILT 2015 CERT/NRG EXAM Page: 69 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 32 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1119138 User-Defined ID:

Cross Reference Number: 239001 K6.02 Topic: ILT-5001A-7b-002 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps* chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(?)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): ON-119, M-1-S-23 Learning PLOT-5001A-7b Objective:

KIA System: 239001 Main and Reheat Importance:

Steam System RO/SRO 3.2 I 3.2 KIA Statement: K6 .. 02 - Knowledge of the effects that a loss or malfunction of the following will have on the MAIN AND REHEAT STEAM SYSTEM: Plant air system REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 70of164 21January2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 33 ID: 1118749 Points: 1.00 Unit 3 RWCU is operating in the Dump Mode to the Main Condenser.

Dump flow is 100 gpm when pressure downstream of CV-55 "Dump Controller" rises to 190 psig.

Based on the above information Dump Flow will?

A lower to O gpm.

B. lower to 50 gpm.

C. lower until downstream pressure is below 190 psig.

D. remain at 100 gpm.

Answer: A Answer Explanation I Choice Basis or Justification Correct: A A downstream pressure of 190 psig will cause an isolation of CV-55. This will cause dump flow to go to 0 gpm.

Distractors: B Plausible if the candidate does not understand that CV-55 only has manual control and believes that there is an automatic feedback mechanism to the control valve.

c Plausible if the candidate does not understand that CV-55 only has manual control and believes that there is an automatic feedback mechanism to the control valve.

D Plausible if the candidate does not understand how the control circuit to CV-55 works or believes that the setpoint for isolation is above 190 psig.

PBS ILT 2015 CERT/NRC EXAM Page: 71 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 33 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1118749 User-Defined ID:

Cross Reference Number: 204000A2.14 Topic: IL T-5012-5g-002 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(5)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): PLOT-5012 Learning PLOT 5012-5g Objective:

K/A System: 204000 Reactor Water Importance Cleanup System RO/SRO 2.9/ 2.9 K/A A 1.07 - Ability to predict and/or monitor changes Statement: in parameters associated with operating the REACTOR WATER CLEANUP SYSTEM controls including: RWCU drain flow REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 72 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 34 ID: 1103560 Points: 1.00

  • A small break LOCA has occurred on Unit 2
  • Drywell pressure is 5 psig and slowly rising
  • Reactor level is +20 inches and being maintained by reactor feedwater

Based on the above conditions, if Torus pressure drops to 1 psig, Torus sprays _ _.(~1~)_automatically isolate and the operator shall (2)

A. (1) will (2) Align RHR for normal using T-204, "Initiation of Containment Sprays Using RHR" return to normal section B. (1) will (2) align RHR for normal operations using SO 10.1.A-2, "Residual Heat Removal System Set Up for Automatic Operation" C. (1)willnot (2) secure Torus sprays using T-204, "Initiation of Containment Sprays Using RHR" D. (1)willnot (2) secure Torus sprays using T-204, "Initiation of Containment Sprays Using RHR" when Torus pressure reaches O psig.

Answer: C Answer Explanation Choice Basis or Justification Correct: c Torus Spray valve M0-2(3)-10-38A(B) does not get an automatic closure signal unless there is a LOCA signal, which there is not. T-204 directs that Torus spray be secured before Torus pressure drops to 2 psig. T-204 also direct the operator how to secure the Torus spray lineup.

Distractors: A Torus Spray valve M0-2(3)-10-38A(B) does not get an automatic closure signal unless there is a LOCA signal, which ther is not. Plausible if the candidate confuses the low pressure logic with the LOCA initiation logic.

B Torus Spray valve M0-2(3)-10-38A(B) does not get an automatic closure signal unless there is a LOCA signal, wich there is not. Plausible if the candidate confuses the low pressure logic with the LOCA initiation logic.

D Torus sprays are to be secured before 2 psig per T-204. Waiting to 0 psig would not be correct. Plausible if the candidate does not understand the requirements of T-204.

PBS ILT 2015 CERT/NRC EXAM Page: 73 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 34 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1103560 User-Defined ID:

Cross Reference Number: 230000A2.14 Topic: ILT 5010-1 Ow-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Psychometrics Comments: Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): T-204, Initiation of Containment Sprays Using RHR Learning PLOT 5010-10w Objective:

KIA System: 230000 RHR/LPCI: Importance:

Torus/Suppression Pool RO/SRO Spray Mode 3.2/ 3.5 KIA Statement: A2.14 - Ability to (a) predict the impacts for the following on the RHR/LPCI: Torus/Suppression Pool Spray Mode; and {b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Low (or negative) suppression pool pressure during system operation REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 74 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 35 ID: 1103704 Points: 1.00

  • The indicating lights for the"A" and "B" Service Water pumps and the "A" and "B" Fuel Pool Service Water Booster pumps are as follows:
  • Green light OFF
  • Red light ON
  • Alarm 216 D-5, "B FUEL POOL SERV WATER BOOSTER PUMP OVERCURRENT" is received.

For the above conditions, what is the required operator response per Alarm Response Card 216 D-5?

A. Trip the "B" Fuel Pool Booster pump.

Place the "C" Fuel Pool Booster pump in-service.

B. Trip the "B" Fuel Pool Booster pump.

Verify the "C" Fuel Pool Booster pump auto starts.

C. Verify the "B" Fuel Pool Booster pump trips.

Place the "C" Fuel Pool Booster pump in-service.

D. Verify the "B" Fuel Pool Booster pump trips.

Verify the "C" Fuel Pool Booster pump auto starts.

Answer: C Answer Explanation Choice Basis or Justification Correct: c When the overcurrent alarm is received the Booster pump should trip. Starting the "C" pump will return system parameters to normal.

Distractors: A Plausible if the candidate does not recall that the Fuel Pool Booster pumps trip when the overcurrent alarm is received. There are pump overcurrent alarms (HPSW for example) that do not trip when the overcurrent alarm is received.

B Plausible if the candidate does not recall that the Fuel Pool Booster pumps trip when the overcurrent alarm is received. There are pump overcurrent alarms (HPSW for example) that do not trip when the overcurrent alarm is received. There is no automatic start of the Fuel Pool Water Booster Pumps. Plausible if the candidate does not recall that the Fuel Pool water Booster pumps do not have an auto start feature like the RBCCW pumps for example.

D There is no automatic start of the Fuel Pool Water Booster Pumps. Plausible if the candidate does not recall that the Fuel Pool water Booster pumps do not have an auto start feature like the RBCCW pumps for example.

PBS ILT 2015 CERT/NRC EXAM Page: 75 of 164 21January2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 35 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 Svstem ID: 1103704 User-Defined ID:

Cross Reference Number: 233000A3.03 Topic: ILT-5019-11-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b )(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): ARC-216 D-5 Learning PLOT-5019-11 Objective:

KIA System: 233000 Fuel Pool Cooling Importance:

and Clean-up RO/SRO 2.6/ 2.6 KIA A3.03 Ability to monitor automatic operations of Statement: the FUEL POOL COOLING AND CLEAN-UP including: System indicating lights and alarms REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 76 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 36 ID: 1103707 Points: 1.00 A hydraulic ATWS exists on Unit 2.

As power is reduced, a Rod Worth Minimizer (RWM) insert rod block occurs.

Based on the above conditions, control rods can be inserted by:

A. placing the Rod Control switch (3A-S2) in the "IN" position B. venting the scram air header in accordance with T-214 "Isolating and Venting the Scram Air Header" C. placing the Emergency In/Notch Override switch (3A-S3) in the "EMERG ROD IN" position ONLY D. bypassing the RWM AND placing the Emergency In/Notch Override switch (3A-S3) in the "EMERG ROD IN" position Answer: D Answer Explanation Choice Basis or Justification Correct: D The RWM must be bypassed to allow the Emergency in switch to continuously insert the control rod.

Distractors: A An insert rod block exists. Normal rod movement with the rod control switch is prevents by the insert block. Plausible if candidate does not understand the relationship between the RWM and RMCS.

B Since a hydraulic ATWS exists, the scram air header is already depressurized. T-214 will have no affect. Plausible if the candidate does not understand that the scram air header would already be depressurized because of the hydraulic ATWS.

c An insert rod block exists. Rod movement with the Emergency In/Notch override switch is prevented without bypassing the RWM. Plausible if candidate does not understand the relationship between the RWM and RMCS.

PBS ILT 2015 CERT/NRG EXAM Page: 77 of 164 21January2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 36 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 0.00 Difficulty:

System ID: 1103707 User-Defined ID:

Cross Reference Number: 201002A4.02 Topic: IL T5062-3f-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps1 1 chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

MEMORY 1OCRF55.41 (b)(6)

Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): T-220, M-1-S-20 Learning PLOT-5062-3f Objective:

KIA System: 201002 Reactor Manual Importance:

Control System RO/SRO 3.5/ 3.5 KIA Statement: A4.02 Ability to manually operate and/or monitor in the control room: Emergency in/notch override switch REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRG EXAM Page: 78of164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 37 ID: 1103715 Points: 1.00 A loss of Feedwater heating has occurred on Unit 3. The following conditions exist:

  • Reactor Power has been lowered to 3500 MWTh per OT-104, "Positive Reactivity Insertion"
  • Computer point NSS318 "Feedwater Temperature" is valid and reads 310 degrees F
  • PMS major alarm "NSS316 "AO 6.7-3 FW Delta T" is NOT in alarm
  • RE-41, "lnstallationNerification of the 30 Monicore Thermal Operating Limits" indicates that the 55 degree F limit is in effect
  • Figure 2 from OT-104 is below for reference Figure 2 FeedwaterTemperature Limits. Unit 3 330 *.......
    • rr ' .. , .. ,. ,.. ...
  • 1 r ******r***c I I I I I I ' '

325 I

320 315 I-- ~ tJ 55 degree Feedwater Temperature Reduction Region  :

310 305 300 295 290 ~

~

-- - J 90 degree Feedwater Temperature J Reduction Region

-~

~

t-- ;=: j

- 285 '-" I u.. 280 ~

-;- 275 ~ ~

ssctegree

~

1TSARegion I ~

270 n; 265

~

260

~

t~~ 1

~ 245 1......

240 im -

1l

- 155 and 90 degree TSARegion I

I if m 225 210 -~

205 -~

200 195 190 ~ ~

=:=1-c

  • t--- -

185 '

180 175 170

~ <D -" -" _.. -" -" -" -" -" -" -" -" -" -" N N N N N N N N N N N N N N W W W ~ W W ~

-.J U"1 0 ........... N w J:>. .t:.. (JI m -.J _,, 00 <O 0 0 ....... N w w ~ c.n Q) en -J co <D CD a ....... N N VJ .;:.. U"I U"10N0-...J(.J1N0-..J(J1N0-...JUlNO"'-ICJ'lNO-...JO'INO-.JO'INO-.JthNO-...JU"INO

\'.Jl o (JI o t.n o c.n o CJ'l o r..n o c.n a c.n a <..n a c.n a c.n a <.l'l a ui a tn o c.n o <..n o Ol a Core Thermal Power (MWth)

Based on the above information, feedwater heating _ _.l~U,..__ symmetrical and operation _ _,{=2,_)_ in the Technical Specification Action (TSA)region.

A. ( 1) is (2) is B. ( 1) is (2) is not C. ( 1) is not (2) is D. (1) is not (2) is not Answer: A PBS ILT 2015 CERT/NRC EXAM Page: 79 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer Explanation Choice Basis or Justification Correct: A OT-104 provides the guidance that if major alarm "NSS316 "AO 6.7-3 FW Delta T" from computer point NSS316 is not in alarm then feedwater heating is symmetrical.

Plotting the point on the graph puts operation in the TSA region.

Distractors: B Plausible if the candidate does not plot the point correctly or does not understand the regions of the graph.

c Plausible if the candidate does not understand the meaning of the alarm.

D Plausible if the candidate does not understand the meaning of the alarm. Plausible if the candidate does not plot the point correctly or does not understand the regions of the graph.

PBS ILT 2015 CERT/NRC EXAM Page: 80 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 37 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1103715 User-Defined ID:

Cross Reference Number: 259001 2.1.19 Topic: ILT-5006-9d-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 1OCRF55.41 (b)(5)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): OT-104 Learning PLOT 5006-9d Objective:

KIA System: 259001 Reactor Importance:

Feedwater System RO/SRO 3.9/ 3.8 KIA Statement: 2.1.19 - Ability to use plant computers to evaluate system or component status REQUIRED None MATERIALS:

Notes and None Comments:

PBS ILT 2015 CERT/NRC EXAM Page: 81 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 38 ID: 1103769 Points: 1.00 The following conditions exist:

  • Due to an equipment malfunction the 2A Recirculation MIG set was "locked up" per SO 2D.7.B-2, "Recirculation MG Set Scoop Tube Lockup and Reset".
  • A reactor scram has occurred
  • Core flow is oscillating between 65% to 75%
  • 2A Recirculation Pump M/G Set Drive Motor amps are oscillating between 250 to 300 amps
  • The PBAPS Power-to-Flow Map is below for reference .

PBAPS POWER FLOW OPERATION MAP

~~  !**

C<QA' F!¢w l"'i Of r-~

li.~tHll Based on the above conditions, what is the status of the 2A Recirculation Pump and what action is required per procedure SO 2D.7.B-2?

The "2A" Recirculation Pump CD cavitating, and the operator shall (2) in accordance with SO 2D.7.B-2, "Recirculation MG Set Scoop Tube Lockup and Reset" A (1) is (2) trip the "2A" Recirc pump B. (1)is (2) runback the "2A" Recirc pump locally C. (1) is not (2) trip the "2A" Recirc pump D. (1) is not (2) runback the "2A" Recirc pump locally PBS ILT 2015 CERT/NRG EXAM Page: 82 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer: A Answer Explanation Choice Basis or Justification Correct: A Core flow and M-G Set amperage oscillations are indications of cavitation. Plotting the position of the Power-to-Flow map would also put operation in the Recirc pump cavitation region. SO 20.7.B-2 direct the operator to trip the Recirc pump following a scram.

Oistractors: B Plausible if the candidate does not recall that SO 20.7.B-2 directs that the operator trip the pump. There are steps in the procedure on when to locally reduce the speed of the M-G set but following a scram in not when that guidance would be used.

c Plausible if the candidate does not understand indications of cavitation or does not plot the operating point correctly on the Power-to-Flow map. Procedure SO 20.7.B-2 requires that the locked up recirc pump be tripped following a reactor scram.

Even of the Recirc pump is not cavitating the procedure requires that the pump must be tripped.

0 Plausible if the candidate does not understand indications of cavitation or does not plot the operating point correctly on the Power-to-Flow map. Plausible if the candidate does not recall that SO 20.7.B-2 directs that the operator trip the pump.

There are steps in the procedure on when to locally reduce the speed of the M-G set but following a scram in not when that guidance would be used.

PBS ILT 2015 CERT/NRG EXAM Page: 83of164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 38 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1103769 User-Defined ID:

Cross Reference Number: 202001 K5.01 Topic: ILT-5002-4a-001 Num Field 1: 2015 NRC Num Field 2:

Text Field:

Comments: Ps~1 chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)

HIGH 10CFR55.41 (b)(7)

Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SO 2D.7.B-2, GP-5 Learning PLOT-5002-4a Objective:

KIA System: 202001 Recirculation Importance:

System RO/SRO 2.7 I 2.8 KIA Statement: K5.01 - Knowledge of the operational implications of the following concepts as they apply to RECIRCULATION SYSTEM: Indication of pump cavitation REQUIRED None MATERIALS:

Notes and None Comments:

PBS IL T 2015 CERT/NRC EXAM Page: 84 of 164 21 January 2015

EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 39 ID: 994128 Points: 1.00 Unit 2 was operating at 2800 MWt when the following transient occurred:

  • The 'A' Recirc Pump tripped
  • The 'B' Recirc Pump speed remains at 1200 RPM
  • Power lowered to 1757 MWt
  • APRMs are oscillating between 48% and 53% power in approximately 4 - 5 second random intervals
  • Indicated Core Flow on FR-2-2-3-095 (Black Pen) is 52 Mlbm/hr
  • Inactive Loop Flow on Fl-2-2-3-092A is 5 Mlbm/hr
  • GP-5-1, "PBAPS Power Flow Operation Map", is below for reference PBAPS POWER FLOW OPER.ATION MAP

,, .,,_,~mnnn -*1-~--~-,_, . ._,,,,. t __,,,_,,,,,,,,, ,_.,j , _,,,,,,,~r-~,,,,,_, .. ,, _,,, Jll* ,~--*---- ..... ,,,.,¥,,,,,,,..,,,_ **vo* *~-* ~,,,,,,,,,....,.......,_

rt .
d $J:  ;;cl ".'CI  :.c:: 9C : 'C*U l 11C*: 1:J

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2 psig. Plausible if the candidate does not recall that HPCI can not be operated in the CST-CST mode above 2 psig. B The RRC will not work because OW press > 2 psig. Plausible if the candidate does not recall that HPCI can not be operated in the CST-CST mode above 2 psig. Plausible if the candidate does not recall the high Torus level swap condition for HPCI. D T-226 will not allow HPCI to be operated in the CST-CST mode it only will bypass a high torus level condition. Plausible if the candidate does not recall the high Torus level swap condition for HPCI. PBS ILT 2015 CERT/NRC EXAM Page: 107 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 49 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994079 User-Defined ID: ILT-5023-1 C-001 Cross Reference Number: 206000K1 .01 Topic: ILT-5023-5c-001 Num Field 1: 2015 NRC Num Field 2: NA Text Field: B Comments: Ps1 chometrics 1 Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(7) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): T-250, RRC-23, T-226 Learning PLOT-5023-5c Objective: K/A System: 295025 High Reactor Importance: Pressure RO/SRO 3.8/ 3/9 K/A Statement: EA 1.04 - Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE: HPCI REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 108of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 50 ID: 1104045 Points: 1.00
  • Unit 2 is at 100% power
  • A small steam leak occurs in the Drywell
  • The PRO transfers "House Loads" as directed by the Control Room Supervisor
  • Drywell pressure suddenly rises to 3 psig
A. trip B. runback to 30% speed C. runback to 45% speed D. continue to operate at the same speed Answer: B Answer Explanation Choice Basis or Justification Correct: B Recirc runsback to 30% based when RPV level drops to 17 inches with the scram signal generated by the high Drywell pressure condition. Distractors: A The Recirc pumps will not trip because house loads had been transferred before the scram and RPV level did not drop to -48 inches. Plausible if the candidate does not recall that transferring house loads prevents the Recirc pump trip on the turbine trip/fast transfer. c Plausible if the candidate does not recall that the run back is to 30% not 45% on the scram. D Plausible if the candidate does not recognize the 3 psig Drywell signal or the -15 inch RPV level conditions as scram signals. PBS ILT 2015 CERT/NRG EXAM Page: 109 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 50 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104045 User-Defined ID: Cross Reference Number: 295006AA1.04 Topic: ILT-5002-3b-003 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps' chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(7) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): ARC-214 B-3 Learning PLOT-5002-3b Objective: KIA System: 295006 SCRAM Importance: RO/SRO 3.1/ 3.2 KIA Statement: AA 1. 04 - Ability to operate and/or monitor the following as they apply to SCRAM: Recirculation system REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 110of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O 51 ID: 1104047 Points: 1.00 Reference the picture below of the HPCI system Panel 20C04B. Based on the HPCI System status, a loss of (1) D.C. has occurred. The HPCI system _ _,..:(2=+,.)_ available. (The answer choices are on the next page) r"- 1 " .r*--c**.*~~
  • i PBS ILT 2015 CERT/NRC EXAM Page: 111 of 164 21 January 2015
EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 A (1) Division I (2) is B. ( 1) Division I (2) is not C. ( 1) Division 11 (2) is D. ( 1) Division 11 (2) is not Answer: D Answer Explanation Choice Basis or Justification Correct: D Division II is the power supply to HPCI. The indicating light being out indicate a loss of D.C. power. Without power to the turbine stop valve, control valve, or flow controller (for example) the HPCI system is not available. Distractors: A Division II is the power supply not Division I. No power to the turbine stop valve, control valve, or flow controller (for example) makes the system unavailable. Plausible if the candidate does not recall the power supply to HPCI or does not correctly interpret the picture and believes that HPCI is available. B Division II is the power supply not Division I. No power to theturbine stop valve , control valve, or flow controller (for example) makes the system unavailable. Plausible if the candidate does not recall the power supply to HPCI. c No power to the turbine stop valve , control valve, or flow controller (for example) makes the system unavailable. Plausible if the candidate does not correctly interpret the picture and believes that HPCI is available. PBS ILT 2015 CERT/NRC EXAM Page: 112 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 51 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104047 User-Defined ID: Cross Reference Number: 295004 AA2.04 Topic: IL T-5057-6c-004 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps1 chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(7) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): E-26, PLOT 5057, PLOT 5023 Learning PLOT-5057-6c Objective: KIA System: 295004 Partial or Importance: complete loss of D.C. RO/SRO Power 3.2/ 3.3 KIA Statement: AA2.04 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: System lineups REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 113of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O 52 ID: 1104051 Points: 1.00
  • A loss of cooling has occurred to the Unit 2 Drywell
  • Drywell temperature is currently 200 degrees F For the above conditions, use the Drywell Spray Initiation Limit Curve below to select the correct statement with respect to Drywell pressure and the ability to spray.
CURVE DW/T-2 DW SPRAY INITIATION LIMIT 600 --*D: 550 u:: 500 0 ~ 450 w ' I- 400 #--+---+-----~ w ~350 a:: ~ 300 ct
'.j 250
J a:i 200 31::
Cl 150 100 0 2 4 6 8 10 12 14 16 DRYWELL PRESSURE <PSIG) Drywell pressure will be approximately _ _.(~1,._)_ psig. Drywell sprays _ _.(~2).__ permitted. A. (1) 2 (2) are B. (1) 2 (2) are NOT C. (1) 8 (2) are D. (1) 8 (2) are NOT Answer: B PBS ILT 2015 CERT/NRG EXAM Page: 114 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer Explanation Choice Basis or Justification Correct: B Without a steam leak Drywell pressure rise will be based solely on the heat up of the Drywell air space. Simulator data shows that when drywell temperature reaches 200 degrees F Drywell pressure will be approximately 2 psig. Plotting 2 psig and 200 degress F is on the UNSAFE side of the Drywell spray curve (left side). The right side of the curve is the SAFE side. Distractors: A Plausible if the candidate does not understand the safe side of the Drywell spray curve. c Plausible if the candidate does not understand the Pressure temperature relationship of the containment. Plausible if the candidate does not understand the safe side of the Drywell spray curve. D Plausible if the candidate does not understand the Pressure temperature relationship of the containment. Plausible if the candidate does not understand the safe side of the Drywell spray curve. PBS ILT 2015 CERT/NRC EXAM Page: 115 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 52 Info Question Type: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104051 User-Defined ID: Cross Reference Number: 295028EA2.04 Topic: IL T-2102-5-003 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps vchometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b )(3) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SE-11, simulator modeling Learning PLOT-2102-5 Objective: KIA System: 295028 High Drywell Importance: Temperature RO/SRO 4.1/4.2 KIA Statement: EA2.04 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell pressure REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 116 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 53 ID: 1104052 Points: 1.00 A transient has occurred on Unit 3 that results in fuel cladding damage. The following conditions exist:
  • The reactor is shut down and all URO and PRO scram actions are complete
  • MSL radiation levels are 5000 mrem/hr and steady
  • 10 minutes after the scram
  • Vent Stack radiation levels are rising
  • Main Stack radiation levels are rising Based on the above information, Vent Stack radiation levels are rising due to a steam leak in the
( 1) and Main Stack radiation levels are rising due to a release from the (2} A. (1) Reactor Building (2) Steam Packing Exhauster B. (1) Reactor Building (2) Off Gas System C. (1) Turbine Building (2) Steam Packing Exhauster D. ( 1) Turbine Building (2) Off Gas System Answer: C Answer Explanation Choice Basis or Justification Correct: c Turbine Building ventilation is always directed to the Vent Stack. A steam leak in the Turbine Building would show on the vent stack. The SPE is always directed to the Main Stack without any hold up time. The radioactive steam for the seals would be exhausted to the Main Stack. Distractors: A A steam leak in the Reactor Building would be directed to the Main Stack via SBGT following the scram. Plausible if the candidate does not recognize the signal to initiate SGBT and isolate Reactor Building ventilation. B A steam leak in the Reactor Building would be directed to the Main Stack via SBGT following the scram. Plausible if the candidate does not recognize the signal to initiate SGBT and isolate Reactor Building ventilation. There is a 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> holdup time on the Off gas system. Radiation levels indicating on the Main Stack would not rise in 1O minutes following the event from the Off gas system. Plausible if the candidate does not recall the function of the off gas system. PBS ILT 2015 CERT/NRC EXAM Page: 117 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O D There is a 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> holdup time on the Off gas system. Radiation levels indicating on the Main Stack would not rise in 10 minutes following the event from the Off gas system. Plausible if the candidate does not recall the function of the off gas system. Question 53 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104052 User-Defined ID: Cross Reference Number: 295038EA2.04 Topic: IL T-2104-5-006 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps *chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): ON-104, T-104 Learning PLOT 2104-5 Objective: KIA System: 295038 High Off-Site Importance: Release Rate RO/SRO 4.1/ 4.5 KIA Statement: EA2.04 Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: Source of off-site release REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 118of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 54 ID: 1109929 Points: 1.00
  • The Crew has entered ON-125, "Loss or Unavailability of Shutdown Cooling" due to a trip of the 2A HPSW pump.
  • The CRS has determined that in order to restore Shutdown Cooling the other HPSW pump in the "A" loop will be started.
Before starting the HPSW pump the operator will direct all personnel to stay clear of the _ _ _ __ A. "B" HPSW pump ONLY B. "C" HPSW pump ONLY C. "B" HPSW pump and the E-22 bus D. "C" HPSW pump and the E-32 bus Answer: D Answer Explanation Choice Basis or Justification Correct: D OP-PB-101-111 section 4 .. 6.6 directs that the operator should announce 4KV pump starts that should include the 4 KV bus powering the pump. The "C" HPSW is the pump in the loop with the "A" HPSW. Distractors: A Plausible if the candidate does not know what the requirement in OP-PB-101-111 is or which pump is in the loop with the "A" RHR pump. B Plausible if the candidate does not know which pump is in the loop with the "A" RHR pump. c Plausible if the candidate does not know what the requirement of OP-PB-101-111. PBS ILT 2015 CERT/NRC EXAM Page: 119 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 54 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 Svstem ID: 1109929 User-Defined ID: Cross Reference Number: 295021 2.1.14 Tooic: ILT-1529-1q-001 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps~ 1 chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): OP-PB-101-111 Learning PLOT-1529-1q Objective: K/A System: 295021 Loss of Importance: Shutdown Cooling RO/SRO 4.6/ 4.6 K/A Statement: 2.1.20 - Ability to interpret and execute procedure steps. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 120 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 55 ID: 1118626 Points: 1.00
  • The station is experiencing a fire in the Radwaste Building El. 135' - 4KV Switchgear Corridor
  • T-357-2, "Area 57 Fire Guide", Attachment 4 is in progress to bypass SV-2-16A-8130A, "ADS Backup Nitrogen A Hdr Supply to Drywell" Performance of Attachment 4 will ensure a long-term nitrogen supply to the -~<~1~)_Safety Relief Valves (SRVs).
Restoring long-term supply to these SRVs (2) meet the T-112, "Emergency Slowdown" requirement for number of relief valves for a blowdown. A. 1) G and K (ONLY) (2) does not B. (1) A, B, and C (ONLY) (2) does not C. (1) A, Band C (ONLY) (2) does D. (1) A, B, C, G and K (2) does Answer: B Answer Explanation I Choice Basis or Justification Correct: B SRVs A, B, and C will be supplied with Nitrogen from the ADS bottles I and 5 SRVs are required for a T-112 blowdown. I Distractors: A Incorrect. ONLY the A, Band C SRVs will be supplied with Nitrogen from the ADS bottles and 5 SRVs are required for a T-112 blowdown. Plausible if the candidate does not understand the purpose of T-357 or the nitrogen supplied by SV-8130A. c Incorrect. ONLY the A, Band C SRVs will be supplied with Nitrogen from the ADS bottles and 5 SRVs are required for a T-112 blowdown. I I Plausible if the candidate does not understand the purpose of T-357 or the nitrogen supplied by SV-8130A. Three SRVs do not meet the T-112 I i I blowdown requirement. Plausible if the candidate does not understand the T-112 blowdown requirements. D Incorrect. SV-8130A does not provide nitrogen to all of the ADS valves. Plausible if the candidate does not understand the purpose of T-357 or the nitrogen supplied by SV-8130A. I PBS ILT 2015 CERT/NRC EXAM Page 121 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 55 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 2.00 System ID: 1118626 User-Defined ID: Cross Reference Number: 600000 2.4.8 Topic: ILT-2112-3-002 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41(b)(10) Source Documentation Source: [8J New Exam Item D Previous NRC Exam D Modified Bank Item D Other Exam Bank D ILT Exam Bank Reference(s): M-333, T-357-2, Area 57 Fire Guide Learning PLOT 2112-3 Objective: KIA System: 600000 Plant Fire on Site Importance: RO/SRO 3.8 I 4.5 KIA Statement: 2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs REQUIRED NONE MATERIALS: Notes and Comments: PBS ILT 2015 CERT/NRC EXAM Page: 122 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O 56 ID: 1104504 Points: 1.00
  • The Nuclear Duty Officer informs Peach Bottom that a Maximum Emergency Generation Alert has been declared.
  • The Off-site electrical lineup is normal.
  • The Transmission System Operator reports the following voltages:
  • Nottingham 220-08 Line 230 kV
  • Cooper 220-08 Line 230 kV
  • Newlinville 220-34 Line 220 kV
  • Peach Bottom # 1 Transformer 13.0 kV In accordance with SE-16, "Grid Emergency", and the associated Table 1, choose the correct action below with regard to Off-site sources.
TABLE 1 OFFSITE SOURCE MINIMUM VOLTAGE ~ewl~nv~lle  ::C-34 Line (3~3SJ) > 13. 51~ kV (:'.. 3 kV side) A. All required off-site sources are operable. Continue to monitor Table 1 voltages. B. One required off-site source is inoperable. Perform ST-0-054-950, "Offsite and Onsite Electrical Power Breaker Alignment and Power Availability Check within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. C. Two required off-site sources are inoperable. Perform ST-0-054-950, "Offsite and Onsite Electrical Power Breaker Alignment and Power Availability Check within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. D. Two required off-site sources are inoperable. Perform a 3.0.3 shutdown. Answer: B PBS ILT 2015 CERT/NRC EXAM Page: 123 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Answer Explanation Choice Basis or Justification Correct: B Voltage on the 220-34 line is below the acceptable value, per SE-16 this makes the circuit INOP. Tech Spec requires that for an INOP offsite circuit that ST-0-054-950, "Offsite and Onsite Electrical Power Breaker Alignment and Power Availability Check" be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Distractors: A The 220-34 line is below the minimum value. Plausible if the candidate does not know how to interpret the table or does not recall that a voltage below the minimum makes the circuit INOP. c The# 1 Transformer voltage is low but that source is not being used to supply power to the 4KV buses so it is not considered when considering operable circuits. Plausible if the candidate does not understand what the normal electrical line is and which sources are providing power to the 4 Kv buses. D The# 1 Transformer voltage is low but that source is not being used to supply power to the 4KV buses so it is not considered when considering operable circuits. Plausible if the candidate does not understand what the normal electrical line is and which sources are providing power to the 4 Kv buses. 3.0.3 shutdown is not the correct action to take for this condition. Plausible if the candidate confused the required actions for offsite circuits INOP with Offsite circuits and DG INOP. PBS ILT 2015 CERT/NRC EXAM Page: 124 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 56 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104504 User-Defined ID: Cross Reference Number: 700000 2.2.42 Topic: ILT-1555-3-019-SE-16 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SE-16, Tech Spec 3.8.1, 3.8.2 Learning PLOT-155-3 Objective: KIA System: 700000 Generator Importance: Voltage and Electric Grid RO/SRO Disturbances 3.9/ 4.6 KIA Statement: 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 125 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 57 ID: 1104525 Points: 1.00
  • Unit 2 is in Mode 5 with refueling activities in progress
  • An irradiated fuel bundle is dropped
  • Reactor Building and Refuel Floor Exhaust Rad monitors indicate as follows:
Reactor Bldg Exhaust Refuel Floor Exhaust Ch. A 10 mR/hr Ch. A 20 mR/hr Ch. B 18 mR/hr Ch. B 10 mR/hr Ch. C 8 mR/hr Ch. C 18 mR/hr Ch. D 22 mR/hr Ch. D 8 mR/hr Based on the above indications, how will Reactor Building Ventilation and SBGT respond? A. Reactor Building AND Refuel Floor Ventilation continue to operate. SBGT does NOT initiate. B. Reactor Building Ventilation isolates. SBGT initiates and aligns to the Reactor Building ONLY. C. Refuel Floor Ventilation isolates. SBGT initiates and aligns to the Refuel Floor ONLY. D. Reactor Building AND Refuel Floor Ventilation isolate. SBGT initiates and aligns to the Reactor Building AND Refuel Floor. Answer: A Answer Explanation Choice Basis or Justification Correct: A GR Ill isolation has NOT occurred. PCIS logic is A or C AND B or D; setpoint is 16 mR/hr (12 mR/hr per ARC). Either RB or RF logic channels will isolate RB AND RF ventilation. In the given conditions, a half-isolation is present from EACH ventilation system, but the isolation signal is NOT complete. Distractors: B GR Ill isolation has not occurred. Plausible if candidate does not understand logic and function of Group Ill isolation. c GR Ill isolation has not occurred. Plausible if candidate does not understand logic and function of Group Ill isolation. D GR Ill isolation has not occurred. Plausible if candidate does not understand logic and function of Group Ill isolation. PBS ILT 2015 CERT/NRC EXAM Page: 126of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 57 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104525 User-Defined ID: 13 CERT Cross Reference Number: 261 OOOA3.03 Topic: IL T-1550-27b-OO 1 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(13) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): GP-8.B; GP-8.B COL Learning PLOT-1550 27b Objective: KIA System: 295023 Refueling Importance: Accident RO/SRO 3.3/ 3.5 KIA AA 1.01 - Ability to operate and/or monitor the Statement: following as they apply to REFUELING ACCIDENTS: Secondary containment ventilation REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 127 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 58 ID: 994686 Points: 1.00
  • The atmosphere in the Main Control Room (MCR) has become contaminated by smoke due to a transformer fire in the North Substation.
  • Shift management has determined that safe operation of the plant is impacted and the use of SCBAs is required due to throat irritation.
  • The smoke is NOT limiting vision.
Based on the above conditions, which of the below statements accurately identifies required actions per SE-17, "MCR Atmosphere Non-Radioactive Contamination"? MCR evacuation i s - - - - - - - - - - - - - - - - A. required. Perform GP-4, Reactor Scram, then enter and execute SE-10, Alternative Plant Shutdown. B. required. Perform GP-4, Reactor Scram, then enter and execute SE-1, Plant Shutdown from the Remote Shutdown Panel. C. NOT required. Secure all MCR ventilation. Enter and execute ON-115, Loss of Normal MCR Ventilation D. NOT required. Place MCR ventilation in the purge mode per SO 400.5.A, Control Room Ventilation Purge Air System Answer: C Answer Explanation Choice Basis or Justification Correct: c Correct. SE-17, MCR Atmosphere Non-Radioactive Contamination, is entered based on determination that safe operations are jeopardized. For the described conditions SE-17 directs securing MCR ventilation and ON-115 entry. Dis tractors: A Incorrect - Presence of an irritant does NOT require immediate MCR evacuation. Conditions at the Remote Shutdown Panel or Alternate Shutdown Panels may not be any different as all plant ventilation draws from the East side of the plant. Evacuation of the MCR is performed ONLY after an assessment of atmospheric conditions at those operating areas and Shift Management determination that the plant cannot be safely operated from the MCR. Plausible if the candidate does not recall the purpose of SE-17 and does not remember the purpose of SE-10. B Incorrect - Presence of an irritant does NOT require immediate MCR evacuation. Conditions at the Remote Shutdown Panel or Alternate Shutdown Panels may not be any different as all plant ventilation draws from the East side of the plant. Evacuation of the MCR is performed ONLY after an assessment of atmospheric conditions at those operating areas and Shift Management determination that the plant cannot be safely operated from the MCR. Plausible if the candidate does not recall the purpose of SE-17 and does not remember the purpose of SE-1. PBS ILT 2015 CERT/NRG EXAM Page: 128 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 D Incorrect - Purge mode will NOT stop intake of contaminated air. Plausible if the candidate does not understand the operation of the purge mode of control room ventilation. Question 58 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficultv: 0.00 Svstem ID: 994686 User-Defined ID: IL T5040D5A004 Cross Reference Number: 295016AK2.03 Tooic: IL T-5040D-4a-004 Num Field 1: 2015 NRC Num Field 2: Text Field: B Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): SE-17, ON-115, PLOT 5040D Learning PLOT5040D-4a Objective: KIA System: 295016 Control Room Importance: Abandonment RO/SRO 2.9/ 3.1 KIA AK2.03 - Knowledge of the interrelations Statement: between CONTROL ROOM ABANDONMENT and the following: Control room HVAC REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 129 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O 59 ID: 1118711 Points: 1.00 Unit 3 is at rated conditions.
  • North Isolation Valve Room temperature is 205 degress F and rising
  • Vent Stack Rl-3979A and Bare indicating 2.5 x 1O -5 µCi/cc and rising
  • The crew has entered T-103, "Secondary Containment Control" Based on the above conditions, which of the following should be isolated in order to eliminate the radiological release?
A. RWCU B. RCIC C. HPCI D. MS IVs Answer: C Answer Explanation Choice Basis or Justification Correct: c The North Isolation Valve Room (NIVR) is the only reactor building area with rising temperature. 200 degrees F is indicative of a primary system steam leak. The HPCI steam supply piping penetrates the Drywell and runs through the North Isolation Valve Room on the way to the HPCI turbine. None of the other systems listed have piping in the NIVR. Rising Vent Stack radiation levels are indicative of a radiation release due to the primary system leak. Distractors: A Incorrect. The RWCU System has no piping that runs through the NIVR. It penetrates the Drywell in the valve pit area which is an elevation above the NIVR. B Incorrect. The RCIC System has no piping that runs through the NIVR. Steam supply piping for RCIC penetrates the Drywell in the Outboard MSIV Room. D Incorrect. The Main Steam Lines penetrate the Drywell in the Outboard MSIV Room. Closing the MSIVs would not eliminate the steam leak in the NIVR. PBS ILT 2015 CERT/NRC EXAM Page: 130 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 59 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1118711 User-Defined ID: Cross Reference Number: 295032EK1 .02 Topic: ILT-2103-?a-002 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41 (b)(12) Source Documentation Source: !XI New Exam Item LJ Previous NRC Exam: D Modified Bank D Other Exam Bank: Item D ILT Exam Bank Reference( s): T-222, T-103 Learning PLOT 2103-?a-001 Objective: KIA System: 295032 - High Importance: Secondary Containment RO/SRO Area Temperature 3.6 I 4.0 KIA Statement: EK1 .02 - Knowledge of the operational implications of the following concepts as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Radiation releases REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 131 of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 60 ID: 1104566 Points: 1.00
  • Unit 2 was being shutdown per GP-3-2 "Normal Plant Shutdown"
  • The URO notes the scram air header pressure lowering and all blue scram lights are lit on the full core display
  • Power initially lowers and is now stabilized at -10%
  • No CRD pumps are available
  • Reactor pressure is 950 psig and steady Which of the following describes an effective method of control rod insertion under the above conditions?
A. Perform T-213, "Scram Solenoid Deenergization". B. Perform T-214, "Isolating and Venting the Scram Air Header". C. Perform T-216, "Control Rod Insertion by Manual Scram or Individual Scram Test Switches". D. Perform T-220, "Driving Control Rods During Failure to Scram". Answer: C Answer Explanation Choice Basis or Justification Correct: c The conditions listed indicate a hydraulic ATWS (Blue lights lit and Scram air header pressure dropping) this eliminates procedures T-213 and T-214 as options. The lack of an operating CRD pump eliminates procedure T-220 as an option. The correct answer is procedure T-216 with the hydraulic ATWS and no CRD pump but RPV pressure above 400 psig. Distractors: A The conditions listed indicate a hydraulic ATWS (Blue lights lit and Scram air header pressure dropping) this eliminates procedures T-213 and T-214 as options. Plausible if the candidate does not understand the indications of a hydraulic ATWS. B The conditions listed indicate a hydraulic ATWS (Blue lights lit and Scram air header pressure dropping) this eliminates procedures T-213 and T-214 as options. Plausible if the candidate does not understand the indications of a hydraulic ATWS. D The lack of an operating CRD pump eliminates procedure T-220 as an option. Plausible if the candidate does not recognize the lack of CRD as a prerequisite for use of T-220. PBS ILT 2015 CERT/NRC EXAM Page: 132 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 60 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104566 User-Defined ID: ILT-2101-7-001 Cross Reference Number: 295015A1 .03 Topic: ILT-2101-5h-003 Num Field 1: 2015 NRC Num Field 2: NIA Text Field: B Comments: Psvchometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41(b)(10) Source Documentation Source: New Exam item Previous NRC Exam XModified Bank Other Exam Bank IL T Exam Bank Reference(s): T-216, T-213, T-214, T-101 Learning PLOT 2101-5h Objective: KIA System: 295015 Incomplete Importance: SCRAM RO/SRO 3.8/ 3.9 KIA Statement: AK2.01 - Knowledge of the interrelations between INCOMPLETE SCRAM and the following: CRD hydraulics REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 133 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 61 ID: 1104593 Points: 1.00 The following conditions currently exist following a small steam leak in the Drywell:
  • Drywell Bulk Average Temperature is 140 degrees
  • Drywell pressure is 2.5 psig
  • Torus pressure is 1.8 psig
  • Drywell Chilled Water Return Header pressure is 26 psig.
The Drywell Chilled Water Saturation and the Drywell Spray Initiation Limit Curves are provided below The question and possible answer choices are on the next page. ~ 300
250
- 225 200'"---'~-'-~-'-~-'--~..I....-~'---'-~-' 0 10 20 30 40 50 60 70 BO D\l\C\\. PJ:TU.:-< HEADER PRESSl"RE O~ Pl-10262 CPSIGl CURVE DW/T-2 DW SPRAY INlTIATION LIMIT 600 550 t 500 ~450 w I- 400 w ~350 cc: IS! 300 j 250 "'200 Cl 150 100 0 2 6 8 10 12 14 16 DRYWELL PRESSURE <PSJGl PBS IL T 2015 CERT/NRC EXAM Page: 134 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Based on the above conditions, what action is required is response to the high Orywell temperature? A. Maximize Orywell Cooling using RRC 44A.1 "Maximize Orywell Cooling" to control Orywell temperature. B. Maximize Orywell Cooling using T-223, "Orywell Cooler Fan Bypass" to control Orywell temperature. C. Spray the Torus using T-204, "Initiation of Containment Sprays Using RHR" to control containment pressure.
0. Spray the Orywell using T-204, "Initiation of Containment Sprays Using RHR" to control containment pressure.
Answer: B Answer Explanation Choice Basis or Justification Correct: B Conditions are on the safe side of the curve to place ventilation in service using T-223. This will provide cooling and help control drywell temperature. This question asks the candidate to determine how Orywell cooling can be placed in-service (increased) with a High Orywell Temperature condition. The candidate must evaluate the operating position on both the Orywell Spray initiation curve and the OW Chilled water saturation curve. The candidate must understand (show knowledge of) what options are available to increase Orywell cooling based on containment conditions. Oistractors: A Orywell pressure is above 2 psig. RRC-44A.1 can not be used because of the trip signal. Plausible if the candidate does not understand that the OW fans trip above 2 psig. c Torus pressure is below the 2 psig pressure to spray the Torus. Plausible if the candidate does not recall the procedural requirement of> 2 psig to spray the Torus. 0 Orywell temperature and pressure are on the unsafe side of the Orywell spray initiation curve. PBS ILT 2015 CERT/NRC EXAM Page: 135 of 164 21January2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 61 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104593 User-Defined ID: Cross Reference Number: 295012AK3.01 Topic: IL T-2102-?g-003 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): T-102, T-223 Learning PLOT-2101-?g Objective: KIA System: 295012 High Drywell Importance: Temperature RO/SRO 3.5/ 3.6 KIA AK3.01 - Knowledge of the reasons for the Statement: following response as they apply to HIGH DRYWELL TEMPERATURE: Increased drywell cooling REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 136 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 62 ID: 1109931 Points: 1.00 An ATWS is in-progress on Unit 2. The following conditions exist:
  • Reactor power is 20%
  • RPV level is being controlled with HPCI and RCIC between -100 and -130 inches
Based on the above conditions, the Main Turbine _ _,,(~1},__ have automatically tripped. The Main Turbine (2} be manually tripped. A. (1) should (2) shall B. (1) should (2) shall not C. (1) should not (2) shall D. (1) should not (2) shall not Answer: A Answer Explanation Choice Basis or Justification Correct: A The Main Turbine should have automatically tripped at 20 inches of vacuum. Any piece of equipment that has exceeded the automatic trip setpoint should be manually tripped. Distractors: B Plausible if the candidate believes that tripping the turbine is not required during an ATWS. c Plausible if the candidate does not recall the trip setpoint for the Main turbine. D Plausible if the candidate does not recall the trip setpoint for the Main turbine. Plausible if the candidate believes that tripping the turbine is not required during an ATWS. PBS ILT 2015 CERT/NRC EXAM Page: 137of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 62 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109931 User-Defined ID: Cross Reference Number: 295002EA1.05 Topic: ILT-1540-2-002-0T-106 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps* *chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b )(7) Source Documentation Source: denser XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): OT-106 Learning PLOT-1540-2 Objective: KIA System: 295002 Loss of Main Importance: Condenser Vacuum RO/SRO 3.2/ 3.2 KIA Statement: AA 1. 05 - Ability to operate and/or monitor the following as they apply to LOSS OF MAIN CONDENSER VACUUM: Main Turbine REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 138 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 63 ID: 1104604 Points: 1.00 Unit 2 is at 100% power when the "C" Reactor Feedpump minimum flow valve fails open. Assuming NO Operator actions, AFTER RPV level stabilizes, Reactor power will be ( 1) , the operator shall (2) A. (1) lower (2) enter GP-2, "Normal Plant Startup" to raise power. B. (1)1ower (2) use GP-5, "Power Operations" to raise power. C. ( 1) higher (2) use GP-5, "Power Operations" to lower power. D. (1) higher (2) enter OT-104, "Positive Reactivity Insertion" to lower power. Answer: D Answer Explanation Choice Basis or Justification Correct: D When the min flow valve fails open it causes feedwater flow to rise to maintain RPV level. This means that feedwater spends less time in the feedwater heaters and feedwater temperature lowers. Colder feedwater into the reactor causes reactor power to rise. An unexpected rise in reactor power is an entry condition into OT-104. Distractors: A Plausible if the candidate does not understand that the rise in feedwater flow causes feedwater temperature to lower. If the candidate does not recall that the heat source is finite and a rise in flow would make temperature lower. B Plausible if the candidate does not understand that the rise in feedwater flow causes feedwater temperature to lower. If the candidate does not recall that the heat source is finite and a rise in flow would make temperature lower. c GP-5 is not the procedure to enter on a transient it should only be entered for steady state operations. Plausible if the candidate does not recall the purpose of GP-5 PBS ILT 2015 CERT/NRC EXAM Page: 139of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 63 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104604 User-Defined ID: Cross Reference Number: 295034 AA2.01 Topic: ILT-1620-2-001. Num Field 1: Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(14) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): OT-104, GP-5 Learning PLOT-1620-2 Objective: KIA System: 295014 Inadvertent Importance: Reactivity Addition RO/SRO 4.1/ 4.2 KIA Statement: AA2.01 - Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION: Reactor power REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 140 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 64 ID: 993739 Points: 1.00 Alarm 226 A-4 "TORUS WATER LEVEL OUT OF NORMAL RANGE" is received. A leak into Primary Containment has caused Torus level to rise to 17.1 feet. The Crew has entered procedure T-102, "Primary Containment Control". Per T-102, "Primary Containment Control", why is continued Reactor operation NOT allowed with Torus level above 17. 1 feet? A. May result in the pressure suppression capability of the containment being insufficient to accommodate an RPV breach by core debris. B. Indicates SRV tailpipe damage will occur if SRVs are opened. C. Will cause primary containment failure during a blowdown due to the torus to drywell vacuum breakers being submerged. D. May exceed the pressure limit of the containment torus access hatches. Answer: A Answer Explanation Choice Basis or Justification Correct: A Receipt of the Torus high level alarm requires the crew to enter TRIP procedure T-102 "Primary Containment Control". Per the TRIP/SAMP Curves, Tables, & Limits - Bases; Torus water level of 17.1 feet is the Maximum Pressure Suppression Primary Containment Water Level (MPSPCWL). Operation with water level above the vent header is not permitted. Distractors: B Plausible this is the bases for the other sections of the curve. c Plausible relates to SRV failure due to high water level which is the bases for the other parts of the curve. D Plausible if the candidate believes that the bases for the high level condition is a loading concern and the candidate does not know the location of the Torus access hatches. PBS ILT 2015 CERT/NRG EXAM Page 141 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 64 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 993739 User-Defined ID: ILT-2102-7A-007 Cross Reference Number: 295029 2.4.31 Topic: IL T-2102-7a-007 SRV Tailpipe Limit Num Field 1: 2015 NRC Num Field 2: N/A Text Field: A Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 10CRF55.41(b)(10) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): T-102 BASES Learning PLOT-2102-7a Objective: KIA System: 295029 High Suppression Importance: Pool Water Level RO/SRO 4.2/ 4.1 KIA Statement: 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 142 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 65 ID: 994762 Points: 1.00
  • Unit 2 is operating at 100% power
  • The 'A' RPS bus was transferred to its alternate power supply
  • After placing all system fans in their normal lineup, Reactor Building and Refuel Floor differential pressures on Panel 20C012 indicate +0.1 inches H2 0 Based on th above conditions, which one of the following actions is correct in accordance with SO 40B.1.A-2?
A remove one Reactor Building Exhaust Fan from service B. place one additional Reactor Building Supply Fan in service C. remove one Refuel Floor Supply Fan from service D. place one additional Equipment Cell Exhaust Fan in service Answer: C Answer Explanation Correct: c Per SO 40B.1.A-2, the normal ventilation system lineup is 1 Equipment Cell exhaust fan, 2 RB supply fans, 2 RB exhaust fans, 2 RF supply fans and 2 RF exhaust fans. Per the SO, if the normal ventilation system lineup does not establish normal differential pressure (-0.1 to -0.4 inches H2 0), the procedure directs removing one RF supply OR exhaust fan from service. In this case, a RF supply fan must be removed from service to establish the proper negative d/p. The question asks the candidate to evaluate the Secondary Containment d/p, determine that the value given is too high for continued operation then determine how to use the secondary containment ventilation system to return building dip to an acceptable value. Distractors: A Since normal differential pressure is -0.1 to -0.4 inches H2 0, removing one RB exhaust fan from service would cause differential pressures to become more positive. Plausible if applicant does not know required d/p range and/or does not understand ventilation system design. B Since normal differential pressure is -0.1 to -0.4 inches H2 0, placing one additional RB supply fan in service would cause differential pressures to become more positive. In addition, SO 40B.1.A-2 gives direction to avoid running 3 RB supply or exhaust fans at the same time. Plausible if applicant does not know required d/p range and/or does not understand ventilation system design. PBS ILT 2015 CERT/NRC EXAM Page: 143 of 164 21January2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 D This would make dip negative, but SO 40B.1.A-2, Caution 4.5.1-1, prohibits running both Equipment Cell exhaust fans. Plausible if applicant does not recall SO 40B.1.A-2 cautions and limitations. Question 65 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 994762 User-Defined ID: ILT-5040B-4B-001 Cross Reference Number: 295035EK3.02 Topic: ILT-5040B-4b-001 Num Field 1: 2015 NRC Num Field 2: Text Field: NRC-09-1 Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): SO 40B.1.A Learning PLOT-5040B-4b-001 Objective: KIA System: 295035 Secondary Importance: Containment High RO/SRO Differential Pressure 3.3/ 3.5 KIA EK3.02 - Knowledge of the reasons for the Statement: following responses as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment ventilation response REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 144 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 66 ID: 994721 Points: 1.00 Which one of the following correctly describes control panel walk-down requirements per OP-AA-103-102, Watchstanding Practices? A Panel walk-downs must be performed as directed and may not be deferred by any individual. B. Shift Manager approval is required to defer panel walk-downs under any conditions. C. The Unit Supervisor can give permission to defer panel walk-downs when plant conditions and/or critical evolutions would be adversely impacted by their performance. D. The Unit RO is authorized to decide when to defer from panel walk-downs if plant conditions and/or critical evolutions would be adversely impacted by their performance. Answer: C Answer Explanation Choice Basis or Justification Correct: c OP-AA-103-102 step 4.4.3 allows the Unit supervisor to defer the panel walkdowns. Distractors: A Plausible if the candidate is not familiar with the OP procedure requirements. B Plausible if the candidate is not familiar with the OP procedure requirements. D Plausible if the candidate is not familiar with the OP procedure requirements. PBS ILT 2015 CERT/NRC EXAM Page: 145 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 66 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 Svstem ID: 994721 User-Defined ID: SROILT15291 D005WATCH Cross Reference Number: 2.1.2 Topic: ILT-1529-1 d-005 Watchstanding Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): OP-AA-103-102 step 4.4.3 Learning 1529-1d Objective: K/A System: 2.1 Conduct of Operations Importance: RO/SRO 4.1/ 4.4 K/A 2.1.2 - Knowledge of operator responsibilities Statement: during all modes of plant operation. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 146 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 67 ID: 993547 Points: 1.00 Which one of the below statements identifies the design bases for the Automatic Depressurization System (ADS)? A Provides a rapid depressurization during small nuclear system breaks allowing steam cooling to protect the fuel barrier. B. Provide a rapid depressurization to prevent a High Pressure Melt Ejection. C. Provides steam cooling during an ATWS to maintain Adequate Core Cooling. D. Provides for depressurization of the Reactor Coolant System during a small break Loss of Coolant Accident (LOCA) if HPCI fails or is unable to maintain the required RPV level. Answer: D Answer Explanation Choice Basis or Justification Correct: D UFSAR states that this is the purpose of ADS. Distractors: A Plausible if the candidate confuses the purpose of ADS with some of the functions of relief valves. B Plausible if the candidate confuses the purpose of ADS with actions taken in the EOP procedures to keep the Reactor depressurized. c Plausible if the candidate confuses the purpose of ADS with some of the functions of relief valves. PBS ILT 2015 CERT/NRC EXAM Page: 147 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 67 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 993547 User-Defined ID: IL T-50018-7-001 Cross Reference Number: 218000K5.01/2.1.27 Topic: ILT-50018-1-001 Identify desiqn bases of ADS system Num Field 1: 2015 NRC Num Field 2: 3 Text Field: B Comments: Ps vchometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41 (b)(8) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): UFSAR, PLOT-5001G Learning PLOT-5001G-1 Objective: KIA System: 2.1 Conduct of Operations Importance: RO/SRO 3.9/ 4.0 KIA 2.1.27 - Knowledge if system purpose and/or Statement: function REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 148 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 68 ID: 1104627 Points: 1.00 It has been determined using OP-AA-108-110, "Evaluation of Special Tests or Evolutions" that an activity scheduled to be performed is a "Special Test". Based on this information, a --'(~1,_)_briefing must be conducted by _ _....(=2,_l_ A. (1) HLA/IPA (2) the Senior Line Manager or Designee B. (1) HLA/IPA (2) Work Execution Control Supervisor C. (1) Tailored Pre-Job (2) the Senior Line Manager or Designee D. (1) Tailored Pre-Job (2) Work Execution Control Supervisor Answer: A Answer Explanation Choice Basis or Justification Correct: A OP-AA-108-110 requires that a HLA/IPA brief be conduced by a Senior line managerorDes~nee Distractors: B Plausible if the candidate does not recall the requirements of OP-AA-108-110. Operations Management does have required actions per the procedure but conducting the brief is not one of them. c Plausible if the candidate does not understand that a Special test requires more than a Pre-Job brief. D Plausible if the candidate does not understand that a Special test requires more than a Pre-Job brief. Plausible if the candidate does not recall the requirements of OP-AA-108-110. Operations Management does have required actions per the procedure but conducting the brief is not one of them. PBS ILT 2015 CERT/NRG EXAM Page: 149 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 68 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1104627 User-Defined ID: Cross Reference Number: 2.2.7 Tooic: ILT-1529-10-001 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): OP-AA-108-110 Learning PLOT-1529-1p Objective: KIA System: 2.2 Equipment Control Importance: RO/SRO 2.9/ 3.6 KIA Statement: 2.2.7 - Knowledge of the process for conducting special or infrequent tests REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 150 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O 69 ID: 993669 Points: 1.00 MA-AA-716-004 "Conduct of Troubleshooting" directs that which of the below organizations will assume the overall Lead for the troubleshooting evolution when the evolution expands beyond Simple Troubleshooting into Complex Troubleshooting? A. Engineering B. Maintenance C. Operations D. Work Control Answer: A Answer Explanation Choice Basis or Justification Correct: A MA-AA-716-004, step 2.11, states that when and where a Troubleshooting evolution expands beyond Simple Troubleshooting into Complex Troubleshooting, Engineering will assume the overall Lead for the Troubleshooting evolution. Distractors: B The Maintenance Organization does have various responsibilities per MA-AA-716-001, but Engineering will assume the overall Lead for the Troubleshooting evolution when and where a Troubleshooting evolution expands beyond Simple Troubleshooting into Complex Troubleshooting. c The Operations Organization does have various responsibilities per MA-AA-716-001, but Engineering will assume the overall Lead for the Troubleshooting evolution when and where a Troubleshooting evolution expands beyond Simple Troubleshooting into Complex Troubleshooting. D The Work Control Organization does have various responsibilities per MA-AA-716-001, but Engineering will assume the overall Lead for the Troubleshooting evolution when and where a Troubleshooting evolution expands beyond Simple Troubleshooting into Complex Troubleshooting. PBS ILT 2015 CERT/NRC EXAM Page: 151of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 69 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 993669 User-Defined ID: ILT-1750-22-001 Cross Reference Number: K 2.2.20 Topic: IL T-1570-15-001 TRT activity Num Field 1: 2015 NRC Num Field 2: N/A Text Field: B Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): MA-AA-716-004 Learning PLOT-1570-15 Objective: KIA System: 2.2 Equipment Control Importance: RO/SRO 2.6/ 3.8 KIA 2.2.20 - Knowledge of the process for managing Statement: troubleshooting activities REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 152 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 70 ID: 993139 Points: 1.00 The Unit 2 Transverse In-core Probe (TIP) Room Area Radiation Monitor(ARM) is indicating 0 mr/hr due to a defective detector. This condition will cause which one of the below sets of indications? A. An alarm will sound in the Main Control Room AND the amber trip light on the local Auxiliary Unit (local to the TIP Room) will illuminate. B. The white downscale light will be illuminated on the Main Control Room ARM Indicator and Trip Unit AND the local klaxon alarm will sound. C. The white downscale light will be illuminated on the Main Control Room ARM Indicator and Trip Unit AND sound an alarm in the Main Control Room. D. The white downscale light will be illuminated on the Main Control Room ARM Indicator and Trip Unit AND the amber trip light on the local Auxiliary Unit (local to the TIP Room) will illuminate. Answer: C Answer Explanation Choice Basis or Justification Correct: c ARC-003 B-5 list the indications that will occur for the given condition, which include MCR alarm 003 B-5 and a white downscale light on actuation device (ARM trip unit) at Panels 20C011 OR OOC014. Distractors: A The local amber trip light will not be lit. The amber light is for a high or upscale condition, not a downscale condition. Plausible if the candidate is not familiar with the indications available for the downscale condition. B The local klaxon alarm will only sound for a high or upsclae condition. Plausible if the candidate is not familiar with the indications available for the downscale condition. D The local amber trip light will not be lit. The amber light is for a high or upscale condition, not a downscale condition. Plausible if the candidate is not familiar with the indications available for the downscale condition. PBS ILT 2015 CERT/NRG EXAM Page: 153of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 70 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 993139 User-Defined ID: ILT-5063C-1A-001 Cross Reference Number: 272000 K1.12/2.3.5 Topic: ILT -5063-3a-OO 1 Num Field 1: 2015 NRC Num Field 2: N/A Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41 (b)(11) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): PLOT5063; ARC-003 B-5 Learning PLOT-5063C-3a Objective: KIA System: 2.3 Radiation Control Importance: RO/SRO 2.9/ 2.9 KIA 2.3.5 - Ability to use radiation monitoring Statement: systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 154 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 71 ID: 1119616 Points: 1.00
  • An Equipment Operator has been assigned to enter the Moisture Separator Area to investigate a steam leak
  • The Equipment Operator has 1800 mR TEDE annual exposure to date
  • Expected dose for investigation of the steam leak is 300 mR In accordance with RP-AA-203,"Exposure Control and Authorization", which one of the following describes the action required, if any, to complete the steam leak investigation based on the above conditions?
A Planned Special Exposure must be obtained. B. Dose Control Level Extension must be obtained. C. Emergency Exposure Extension must be obtained. D. No action required because the Equipment Operator's total exposure will be less than 4000 mR. Answer: B Answer Explanation Choice Basis or Justification Correct: B Per RP-AA-203 requires dose extension above 2000 mR TEDE. Dose extensions are granted in 500 mR increments. Distractors: A Incorrect - RP-AA-203 requires dose extension above 2000 mR TEDE. Dose extensions are granted in 500 mR increments. This evolution does not qualify as a Planned Special Exposure or Emergency Exposure Extension. Plausible if the candidate is not familiar with the radiation exposure limits. c Incorrect - RP-AA-203 requires dose extension above 2000 mR TEDE. Dose extensions are granted in 500 mR increments. This evolution does not qualify as a Planned Special Exposure or Emergency Exposure Extension. Plausible if the candidate is not familiar with the radiation exposure limits. D Incorrect - RP-AA-203 requires dose extension above 2000 mR TEDE. Dose extensions are granted in 500 mR increments. This evolution does not qualify as a Planned Special Exposure or Emergency Exposure Extension. Plausible if the candidate is not familiar with the radiation exposure limits. PBS ILT 2015 CERT/NRG EXAM Page: 155 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 71 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1119616 User-Defined ID: ILT-1730-4-003 Cross Reference Number: 2.3.4 Topic: IL T-1730-4-003 Exposure control Num Field 1: 2015 NRC Num Field 2: 0.00 Text Field: IL T05-1 NRC Exam #72 Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(12) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): RP-AA-203, Exposure Control and Authorization Learning PLOT 1730-4 Objective: KIA System: 2.3 Radiation Control Importance: RO/SRO 3.2/ 3.7 KIA 2.3.4 - Knowledge of radiation exposure limits Statement: under normal and emergency conditions. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 156 of 164 21January2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 72 ID: 1104646 Points: 1.00 A loss of off-site power has occurred. Per SE-11, "Loss of Off-site Power", who must be notified of the loss of off-site power and informed of Peach Bottom Station status. A Nuclear Reglatory Commission B. Transmission System Operator C. Federal Energy Regulatory Commission D. Pennsylvania Bureau of Radiation Protection Answer: B Answer Explanation Choice Basis or Justification Correct: B Per SE-11 "Loss of Off-site Power" the Transmission System Operator should be informed of the loss of power and pertinent information that will assist him in restoring an outside power source to PBAPS. He should also be aware of any other degraded conditions at PBAPS. Distractors: A Plausible if the candidate confuses SE-11 requirements with EP notification requirements. c Plausible if the candidate confuses SE-11 requirements with EP notification requirements. D Plausible if the candidate confuses SE-11 requirements with FERG notification requirements. PBS ILT 2015 CERT/NRC EXAM Page: 157of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 72 Info Question Tvpe: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 Svstem ID: 1104646 User-Defined ID: Cross Reference Number: 2.4.30 Topic: ILT-1555-5-001 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psvchometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SE-11 Learning PLOT-1555-5 Objective: KIA System: 2.4 Emergency Importance: Procedures RO/SRO 2.7/ 4.1 KIA Statement: 2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 158of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 73 ID: 1104651 Points: 1.00
  • HPCI testing is in progress on Unit 2
  • Unit 2 Torus temperature is 96 degrees F and rising Based on the above information, choose the correct statement below.
T-102, "Primary Containment Control" shall _ _ _ _ _ _ _ __ A. be entered. T-102 can be exited when it is determined that an emergency does not exist. B. be entered. T-102 can be exited only after Torus Temperature is less than 95 degrees F. C. NOT be entered. Per Technical Specifications, secure HPCI immediately. D. NOT be entered. Per Technical Specifications, secure HPCI when Torus temperature is 100 degrees F. Answer: A Answer Explanation Choice Basis or Justification Correct: A Per the TRIP T-BAS (Intro); "HPCI testing can result in the occurrence of a T-102 high Torus temperature entry condition. Once it is determined that the elevated temperature is due only to the test in progress, T-102 may be exited, even if the Torus temperature is still above the entry condition setting. Distractors: B Plausible if the candidate is not familiar with the Trip implementation procedure and believes that Torus temperature must be returned below the entry condition before T-102 can be excited. c Plausible if the candidate is not familiar with the Trip implementation procedure. The Tech Spec requirement to secure any system adding heat to the torus is 105 degrees F. D Plausible if the candidate is not familiar with the Trip implementation procedure. The Tech Spec requirement to secure any system adding heat to the torus is 105 degrees F. PBS ILT 2015 CERT/NRC EXAM Page: 159of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 73 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1104651 User-Defined ID: Cross Reference Number: 2.4.14 Topic: ILT-1560-6-001 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): T-BAS Introduction to TRIP and SAMP Bases Learning PLOT-1560-6 Objective: KIA System: 2.4 Emergency Importance: P raced ures/Plan RO/SRO 3.8/ 4.5 KIA Statement: 2.4.14 - Knowledge of general guidelines for EOP usage REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 160 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 74 ID: 1104709 Points: 1.00 Prior to a startup on Unit 3 the following Wide Range Neutron Monitor (WRNM) readings are recorded in GP-2, "Normal Startup": WRNM A 20 WRNM C 25 WRNM E 20 WRNM G 28 WRNM B 25 WRNM D 30 WRNM F 27 WRNM H 30 Per GP-2 guidance the operator can expect criticality between _ _.(._,_1),__cps and _ _,(=2,_)_cps. A. (1) 2,560 (2) 10,240 B. (1) 2,560 (2) 15,360 C. (1) 3,840 (2) 10,240 D. (1) 3,840 (2) 15,360 Answer: B Answer Explanation Choice Basis or Justification Correct: B Startup procedure GP-2 states that the reactor should go critical between 7 and 9 doublings of the lowest and highest count rates respectively. Distractors: A Plausible if the the candidate does not recall that 7 to 9 doubling rule in GP-2 or doesn't remember that it is the lowest and highest count rates used to determine the values. c Plausible if the the candidate does not recall that 7 to 9 doubling rule in GP-2 or doesn't remember that it is the lowest and highest count rates used to determine the values. D Plausible if the the candidate does not recall that 7 to 9 doubling rule in GP-2 or doesn't remember that it is the lowest and highest count rates used to determine the values. PBS ILT 2015 CERT/NRC EXAM Page: 161 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision O Question 74 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1104709 User-Defined ID: Cross Reference Number: 2.2.1 Topic: IL T-1530-5-001 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): GP-2 Learning PLOT-1530-5 Objective: KIA System: 2.2 Equipment Control Importance: RO/SRO 4.5/ 4.4 KIA 2.2.1 - Ability to perform pre-startup procedures Statement: for the facility, including operating those controls associated with plant equipment that could affect reactivity. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 162of164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 75 ID: 1118810 Points: 1.00 A Unit 2 Reactor Operator position turnover has been completed. In accordance with OP-M-112-101, "Shift Turnover and Relief', the on-coming Reactor Operator is required to announce shift turnover and relief to: A. Shift Manager B. Unit Supervisor C. The Plant Reactor Operator D. The entire shift crew Answer: B Answer Explanation Choice Basis or Justification Correct B Per OP-M-112-101 "Shift Turnover and Relief', section 4.8 "Reactor Operator Shift Turnover Responsibilities", after relief, the on-coming Reactor Operator should announce shift turnover and relief to the Unit Supervisor. Dis tractors: A Incorrect - After relief, the on-coming Reactor Operator should announce shift turnover and relief to the Unit Supervisor c Incorrect - After relief, the on-coming Reactro Operator should announce shift turnover and relief to the Unit Supervisor D Incorrect - After relief, the on-coming Reactor Operator should announce shift turnover and relief to the Unit Supervisor PBS ILT 2015 CERT/NRC EXAM Page: 163 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Reactor Operator Exam - Revision 0 Question 75 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 Svstem ID: 1118810 User-Defined ID: ILT-1529-1 D-008 Cross Reference Number: 2.1.3 Tooic: ILT-1529-1 d-008 Turnover Num Field 1: 2015 NRC Num Field 2: N/A Text Field: B Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.41(b)(10) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): OP-AA-112-101 Learning PLOT-1529-1d Objective: KIA System: 2.1 Conduct of Operations Importance: RO/SRO 3.7/3.9 KIA 2.1.3 - Knowledge of shift or short-term relief Statement: turnover practice. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 164 of 164 21 January 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 1 ID: 994708 Points: 1.00
  • A fire in the Main Control Room on the Unit 2 side results in entry into SE-10 "Alternative Shutdown".
  • Immediate operator actions are taken and control of both units is established at the Alternative Shutdown (ASD) Panels.
Which one of the following describes the required procedural actions the crew should take to control RPV water level? A Utilize SE-10 for directions to control RPV level. Do NOT enter T-101"RPV Control". B. Utilize SE-10 for directions to control RPV level. Enter T-101 "RPV Control" and perform concurrently. C. Utilize SE-1 O for directions to control RPV level. Enter T-101 "RPV Control", RC/L only. D. Exit SE-10 for directions to control RPV level. Enter T-101 "RPV Control", RC/L only. Answer: A Answer Explanation Choice Basis or Justification Correct: A In order to maintain configuration control and avoid conflicting guidance, the SE-10 Bases directs that the use of the TRIP procedures be suspended once SE-10 is entered. SE-10 shall be utilized and T-101 shall not be entered. Distractors: B Plausible if the candidate does not recall the requirement to execute SE-10 exclusively. c Plausible if the candidate does not recall the requirement to execute SE-10 exclusively. D Plausible if the candidate does not recall the requirement to execute SE-10 exclusively. PBS ILT 2015 CERT/NRC EXAM Page: 1 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994708 User-Defined ID: ILT15557003SE10T101 Cross Reference Number: 295016 2.2.14 Topic: IL T-1555-7-003-SRO-SE 10 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): SE-10 Bases, T-101 Bases Learning PLOT 1555-7 Obiective: KIA System: 295016 Control Room Importance: Abandonment RO/SRO 4.3/ 4.4 KIA Statement: 2.1.23 - Ability to perform specific system and integrated plant procedures during all mode of plant operation. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 2 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 2 ID: 1109936 Points: 1.00
  • Unit 3 is at 85% power with a reactor startup in-progress.
  • A0-3-02-80A "Inboard MSIV" closes.
Based on the above, reactor pressure will _ _.(~1.,,_)_and the crew shall _ _.(~2),__ A (1) rise (2) enter OT-102, "Reactor High Pressure" and reduce Reactor Power until Total Steam Flow to less than 10.8 Mlbs/hr. B. (1) rise (2) enter OT-102, "Reactor High Pressure" and reduce Reactor Power until Total Steam Flow to less than 12.2 Mlbs/hr. C. ( 1) remain the same (2) continue the GP-2, "Normal Plant Startup to 95%. D. (1) remain the same (2) maintain Reactor power until the MSIV can be re-opened using SO 1A.7.B-3, "Main Steam Line Recovery" Answer: A Answer Explanation Choice Basis or Justification Correct: A Reactor power of 85% is higher than three main steam lines can pass and will result in RPV pressure rising. The rise in RPV pressure from 85% is enough for an operator to enter OT-102. The followup action in OT-102 is lower Reactor power low enough to re-establish the margin to the Main Steam Line high flow isolation. Reducing total steam flow to 10.8 Mlbs/hr ensures that each steam line flow is reduced back to maintaining the maximum individual value of 3.6 Mlbs/hr. Dis tractors: B Plausible if the candidate believe that the value was adjusted for EPU. EPU Implementation does not change the values listed in the chart above for the number of unisolated steam lines because the safety analyses only supports Main Steam Line isolation at a power level of up to 75% of 3514 MWt (2635.5 MWt). understand the response time from 85% power. c Plausible if the candidate does not understand that three Main Steam lines cannot support 85% reactor power without reactor pressure rising. D Plausible if the candidate does not understand that three Main Steam lines cannot support 85% reactor power without reactor pressure rising. PBS ILT 2015 CERT/NRC EXAM Page: 3 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 2 Info Question Tvpe: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109936 User-Defined ID: Cross Reference Number: 295020AA2.04 Topic: ILT-5007G-5g-001 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps* chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.41 (b)(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): OT-102 Learning PLOT 5007G-5g-001 Objective: KIA System: 295020 Inadvertent Importance: Containment Isolation RO/SRO 3.9 / 3.9 KlA Statement: AA2.04 - Ability to determine and/or interpret the following as they apply to INADVERTENT CONTAINMENT ISOLATION: Reactor pressure REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 4 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O 3 ID: 994782 Points: 1.00 The following conditions exist on Unit 3:
  • The crew is executing procedure T-111 "Level Restoration"
  • An emergency depressurization is in progress with 5 SRVs open
  • RPV level is -190 inches and slowly lowering
  • RPV pressure is 550 psig and slowly lowering
  • The 3A Core Spray pump is the only available source of injection Based on these conditions, Adequate Core Cooling (ACC) is {1) maintained and the Control Room Supervisor should {2)
A (1) being (2) continue to execute T-111, "Level Restoration" B. (1) being (2) exit T-111, "Level Restoration" and enter and execute T-101, "RPV Control" C. (1) NOT being (2) continue efforts to restore ACC via submergence using T-111, "Level Restoration" D. ( 1) NOT being (2) exit T-111, "Level Restoration" and enter and execute the SAMPs Answer: A Answer Explanation Correct: A When RPV water level cannot be maintained above the top of active fuel TAF (-172 inches), adequate steam flow (cooling) is established by maintaining RPV water level above the Minimum Steam Cooling RPV Water Level (-195 inches), as long as RPV pressure is above the Minimum Steam Cooling Pressure (270 psig with 5 SRVs open). Operation should continue until RPV level is recovered or until a decision is made that ACC is no longer assured then the evaluation to go to SAMPs would be made. Distractors: B ACC is being maintained but since RPV level is not recovered above TAF, T-101 is not entered. Plausible if the candidate does not understand the requirement to stay in T-111 until RPV level is recovered above TAF. c Plausible if the candidate does not recognize that the conditions for steam cooling are met. D Plausible if the candidate does not recognize that the conditions for steam cooling are met. Plausible if the candidate believes that ACC is not met and that the entry into SAMPs is required. ~- PBS ILT 2015 CERT/NRC EXAM Page: 5 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994782 User-Defined ID: IL T-2111-4-002 Cross Reference Number: 295031 EA2.04 Topic: ILT-2111-4-003 Num Field 1: 2015 NRC Num Field 2: Text Field: NRC-09-1 Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b )(5) Source Documentation Source: New Exam item Previous NRC Exam XModified Bank Other Exam Bank ILT Exam Bank Reference(s): T-BAS (Intro); TRIP/SAMP Curves, Tables & Limits Bases; T-111 and Bases Learning PLOT-2111-4 Objective: KIA System: 295031 Reactor Low Importance: Water Level RO/SRO 4.6/ 4.8 KIA Statement: EA2.04 - Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 6 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 4 ID: 1110315 Points: 1.00 Unit 2 is in a refueling outage. The following conditions exist:
  • The reactor is in Mode 4
  • The "B" loop of RHR is blocked for maintenance
  • The "B" loop of Core Spray is blocked for Maintenance
  • The "A" Core Spray loop is available for injection
  • Maintenance has a Work Order activity to lower Torus level to 10 feet.
Maintenance -~(~1,._}_proceed with the activity. The "A" loop of Core Spray -~+--"Protected !2} Equipment" per OP-AA-108-117, "Protected Equipment Program". A ( 1) can (2) is B. (1) can (2) is not C. (1) can not (2) is D. (1) can not (2) is not Answer: c Answer Explanation Choice Basis or Justification Correct: c Lowering Torus level to 10 feet will INOP Core Spray and RHR. Core Spray and RHR are the Tech Spec required injection system in Mode 4. For this reason maintenance can not continue with their activity. Per OP-AA-108-117 section 4.2 Core Spray would be protected equipment. Distractors: A Plausible if the candidate does not understand that lowering Torus level to 10 feet will INOP ECCS due to exceeding the vortex limit. B Plausible if the candidate does not understand that lowering Torus level to 10 feet will INOP ECCS due to exceeding the vortex limit. Plausible if the candidate does not understand the requirements to protect SSC equipment. D Plausible if the candidate does not understand the requirements to protect SSC equipment. PBS ILT 2015 CERT/NRG EXAM Page: 7 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1110315 User-Defined ID: Cross Reference Number: 295030 2.2.18 Topic: ILT-1529-1 r-001-SRO Num Field 1: Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b )(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): OP-AA-108-117, Tech Specs Learning PLOT-1529-1 r Objective: KIA System: 295030 Low Suppression Importance: Pool Water Level RO/SRO 4.0/ 4.7 KIA Statement: 2.2.22 - Knowledge of limiting conditions for operations and safety limits. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 8 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 5 ID: 994310 Points: 1.00
  • Unit 3 is at 25% power
  • An explosion ruptures several Instrument Air lines in the turbine building
  • All available air compressors are running
  • Instrument Air pressure is 65 psig and lowering.
  • Scram Air header pressure is 45 psig. Control rods begin to drift in In accordance with ON-119 "Loss of Instrument Air", for the above conditions, the crew must scram and use to control RPV level.
A Feedwater per procedure T-100 "Scram". B. HPCI and/or RCIC per procedure T-100 "Scram". C. Feedwater per procedure T-101 "RPV Control". D. HPCI and/or RCIC per procedure T-101 "RPV Control". Answer: B Answer Explanation Choice Basis or Justification Correct: B ON-119 directs entry into T-100. Without an air supply the outboard MSIVs will close. HPCI/ RCIC are the systems available to supply water to the RPV when the MSIVs are closed. Distractors: A Plausible if the candidate does not recall that a loss of instrument air will cause the MSIVs to go closed an remove Feedwater as an injection source. c Plausible if the candidate does not recall that ON-119 requires entry into T-100 not T-101. Plausible if the candidate does not recall that a loss of instrument air will cause the MSIVs to go closed and remove Feedwater as an injection source. D Plausible if the candidate does not recall that ON-119 requires entry into T-100 not T-101. PBS ILT 2015 CERT/NRG EXAM Page: 9 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994310 User-Defined ID: Cross Reference Number: 295019 2.1.20 Topic: IL T-1550-22C-002-SRO Num Field 1: 2015 NRC Num Field 2: 0.00 Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 10CRF55.43(b)(5) Source Documentation Source: New Exam item Previous NRC Exam XModified Bank Other Exam Bank IL T Exam Bank Reference( s ): ON-119, T-100, T-101 Learning PLOT-1550-22c Objective: KIA System: 295019 Partial or Importance: Complete Loss of RO/SRO Instrument Air 4.6/ 4.6 KIA Statement: 2.1.20 - Ability to interpret and execute procedure steps. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 10 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O 6 10:993503 Points: 1.00 Unit 2 and Unit 3 are at full power with all systems operable and in their normal full power lineup. The E42 Bus was de-energized to allow for emergent repair of a hot spot that had developed in a bus connection. How long can this bus remain de-energized before a Technical Specification condition is entered that requires shutdown of Unit 2? A. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. 7 days Answer: B Answer Explanation Choice Basis or Justification Correct: B The E-42 bus is one of the required Unit 2 electrical power distribution subsystems require by Tech Spec section 3.8.7, Distribution System - Operable. With one Unit 2 AC electrical power distribution subsystem inoperable, power must be restored to operable status in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. (3.8.7.C) Distractors: A Plausible if the candidate does not understand that the E-42 bus is on of the required Unit 2 AC subsystems. c Plausible if the candidate does not understand that the E-42 bus is on of the required Unit 2 AC subsystems. D Plausible if the candidate does not understand that the E-42 bus is on of the required Unit 2 AC subsystems. PBS ILT 2015 CERT/NRC EXAM Page: 11 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 6 Info Question Type: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficultv: 1.00 System ID: 993503 User-Defined ID: Cross Reference Number: 295003 AA2.02 Topic: ILT-5054-002 TS - de-enerqize 4 KV bus Num Field 1: 2015 NRC Num Field 2: NA Text Field: B Comments: Ps* 'Chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 10CRF55.43(b)(2) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference( s): Tech Spec 3.8.7 Learning PLOT-1555-4 Objective: KIA System: 295003 Partial or Importance: Complete Loss of RO/SRO AC.Power 4.1/ 4.4 KIA Statement: 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation REQUIRED Tech Spec 3.8 MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 12 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 7 ID: 1006403 Points: 1.00 The following conditions exist on Unit 3:
  • TBCCW pumps have been tripped due to a system leak
  • Reactor power has been lowered to 58% using procedure GP-9-2 "Fast Reactor Power Reduction"
  • The following Condensate Pump related computer points are in alarm:
W018 indicates 193 degrees F W019 indicates 176 degrees F W022 indicates 183 degrees F W023 indicates 190 degrees F W026 indicates 191 degrees F W027 indicates 182 degrees F Portions of ON-118 "Loss of TBCCW" are PROVIDED BELOW AND ON THE NEXT PAGE:
2. 1 IF Ji..NY component must be removed from service OR trips AND the loss of this component makes a Unit trip likely, THEN PERFORM GP-4, "Manual Reactor Scram, concurrently with this procedure.
2.8 IF any of the following conditions occur, THEN REDUCE reactor power in accordance with GP-9-2(3), "Fast Reactor Power Reduction", AND REMOVE the affected pump(s) from service. 2.8.1 Any Condensate Pump thrust bearing temperature at OR above 190 F. 2.8.2 Any condensate Pump or motor bearing temperature at OR above 190 F. 2.8.3 Any Condensate Pump vibration exceeding the alarm setpoint. PBS ILT 2015 CERT/NRC EXAM Page: 13 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 TABLE 1 CONDENSATE PUMP /MOTOR THRUST BEARING TEMPERl1.TURE POINTS COMPUTER POINT (*)F) POINT ID ALARM "A" CONDENSATE PUMP MOTOR THRUST BRG. W018 (W318) l 75oF (l 75°F) "P.. 11 CONDENSATE PUMP THRUST BRG. W019 (W319) 200°F (200°F) "B" CONDENSATE PUMP MOTOR THRUST BRG. W022 (W322) 175°F (175°F) "B" CONDENSATE PUMP THRUST BRG. W023 (W323) 200°F (200°F) ncn CONDENSATE PUMP MOTOR THRUST BRG. W026 (W326) 175°F (175°F) H (~ 11 CONDENSATE PUMP THRUST BRG. W027 (W327) 200°F (2 00 °F) Based on the above conditions, which one of the following is the correct course of action for these conditions? A. Further reduce power per GP-9-2 "Fast Reactor Power Reduction" and remove the 2A and 2C Condensate Pumps from service ONLY. B. Further reduce power per GP-9-2 "Fast Reactor Power Reduction" and remove ALL Condensate pumps from service. C. Perform GP-4 "Manual Reactor Scram" and remove the 2A and 2C Condensate pumps from service ONLY. D. Perform GP-4 "Manual Reactor Scram" and remove ALL Condensate Pumps from service. Answer: D Answer Explanation Choice Basis or Justification Correct: D Computer points W018, W023 and W026 show that the 2A, 2B and 2C condensate pumps must be removed from service since all have motor or thrust bearing temperature that are "at or above 190 degrees F". Since further power reduction using GP-9-2 cannot reduce power enough to remove ALL condensate pumps from service, a GP-4 manual scram is required. This is based on the guidance of ON-118 step 2.1 that directs a GP-4 manual scram if the loss of any component makes a unit trip likely. ~* Distractors: A All 3 condensate pumps have exceeded the temperature limit for continued operation and must be removed from service. Further power reduction using GP-9-2 will not reduce power enough to remove all condensate pumps from service. Therefore, a GP-4 manual scram is required. PBS ILT 2015 CERT/NRC EXAM Page: 14 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 B Further power reduction using GP-9-2 will not reduce power enough to remove all condensate pumps from service. Therefore, a GP-4 manual scram is required. c All 3 condensate pumps have exceeded the temperature limit for continued operation and must be removed from service. Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1006403 User-Defined ID: 13 CERT Cross Reference Number: 295018 2.1.19 Topic: IL T 1550-21 a-001-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time SRO Knowledge Allowance (minutes) HIGH 10CFR55.43(b)(5) Source Documentation Source: LJ New Exam Item LJ Previous NRC Exam: D Modified Bank Item D Other Exam Bank: ~ ILT Exam Bank Reference ON-118 and Bases (s): Learning PLOT-PBIG-1550-21a Objective: K/A 295018 - Partial or Total Importance: System: Loss of CCW SRO 3.8 K/A Statement: 2.1.19 - Ability to use plant computers to evaluate system or component status. REQUIRED NONE MATERIALS: Notes and Comments: PBS ILT 2015 CERT/NRC EXAM Page: 15 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 8 ID: 1120210 Points: 1.00 Unit 3 is operating at 100% power when the following occurs:
  • An Equipment Operator reports a large steam break in the Unit 3 Reactor Building
  • Annunciator 317 K-5, "Reac Bldg. Hi-Lo Diff Pressure" alarms
  • Annunciator 317 L-1 "Reac Bldg. Refueling Area Hi-Lo Diff Press" alarms
  • Reactor Building and Refuel Floor vent exhaust radiation readings are 1 mr/hr
  • RPV level is -25 inches and steady
  • The Shift Manager has declared a Site Area Emergency (SAE) for an Unisolable Main Steam Line break.
Based on the above conditions, Reactor Building pressure will be (1) The Crew shall (2) A (1) positive (2) reduce Secondary Containment temperature/pressure using T-222, "Secondary Containment Ventilation Bypass per T-103, "Secondary Containment Control". B. ( 1) positive (2) Depressurize the Reactor using ST-0-080-500, "Recording and Monitoring Reactor Vessel Temperatures and Pressure" per T-104, "Radioactivity Release". C. (1) negative (2) reduce Secondary Containment temperature/pressure using T-222, "Secondary Containment Ventilation Bypass per T-103, "Secondary Containment Control". D. (1) negative (2) Depressurize the Reactor using ST-0-080-500, "Recording and Monitoring Reactor Vessel Temperatures and Pressure" per T-104, "Radioactivity Release". Answer: A Answer Explanation Choice Basis or Justification Correct: A The Reactor Building will be positive with the report of a large steam break in the reactor building and the Hi-lo Differential pressure alarms. T-103 "Secondary Containment Control" must be entered out of the AR Cs listed for the high Secondary Containment pressure condition. With low radiation levels, T-103 will drive performance of T-222 to restore RB ventilation and reduce RB temperature and pressure. Distractors: B Plausible if the candidate confuses the T-104 entry based on a Radiation Release EAL and the declared EAL on a Main Steam Line Break. The action of performing a GP-4 shutdown is an action if radiation levels are above the EAL Alert level. The Shift Manager has declared a SAE. If the candidate does not understand that the declaration must be on radiation release the action for T-104 is plausible. PBS ILT 2015 CERT/NRC EXAM Page: 16 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 c Plausible if the candidate does not understand that the listed conditions will cause Reactor Building pressure to go positive. The Reactor Building will stay negative if a small steam leak occurs in the secondary containment however with the report of a steam line break the building will go positive. Additionally the annunciators received are for both a high or low differential pressure condition. The candidate must make the determination based on the rest of the conditions that the pressure would be high and not low. D Plausible if the candidate does not understand that the listed conditions will cause Reactor Building pressure to go positive. The Reactor Building will stay negative if a small steam leak occurs in the secondary containment however with the report of a steam line break the building will go positive. Additionally the annunciators received are for both a high or low differential pressure condition. The candidate must make the determination based on the rest of the conditions that the pressure would be high and not low. Plausible if the candidate confuses the T-104 entry based on a Radiation Release EAL and the declared EAL on a Main Steam Line Break. The action of performing a GP-4 shutdown is an action if radiation levels are above the EAL Alert level. The Shift Manager has declared a SAE. If the candidate does not understand that the declaration must be on radiation release the action for T-104 is plausible. Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1120210 User-Defined ID: ILT-2103-1-006 Cross Reference Number: 295035EA2.01 Topic: ILT-2103-2-008-SRO Num Field 1: 2015 NRC Num Field 2: N/A Text Field: A Comments: Ps 1chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): T-103, T-104, T-222 Learning PLOT-5009-2b Objective: PBS ILT 2015 CERT/NRC EXAM Page: 17 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRG Senior Reactor Operator Exam - Revision 0 K/A System: 295035 Secondary Importance: Containment High RO I SRO Differential Pressure 3.8/ 3.9 K/A Statement: EA2.01 - Ability to determine and/or monitor the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment pressure REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 18 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O 9 ID: 1109846 Points: 1.00 Unit 2 has been at 100% power for 300 days. The following conditions exist:
  • Fuel bundles are being moved in the Unit 2 fuel pool in preparation for loading of an ISFSI cask
  • ST-0-09A-325-2, "Standby Gas Treatment (SBGT) Subsystem Operability Test" is in progress when the "A" SBGT Fan runs for 10 minutes and then trips on overcurrent For the above conditions, (1) What is the Technical Specification required action?
Per the Technical Specification bases, the SBGT System is needed to mitigate the consequences (2) A. (1) Suspend movement of fuel bundles in the Fuel Pool. (2) of a Fuel Handling Accident. B. ( 1) Place the "B" SBGT fan in service immediately. (2) of a Fuel Handling Accident. C. (1) Place the "B" SBGT fan in service immediately. (2) from a radiation release caused by a OBA LOCA.
0. (1) Restore SBGT subsystem to operable in 7 days.
(2) from a radiation release caused by a OBA LOCA. Answer: 0 Answer Explanation Choice Basis or Justification Correct: 0 The "A" SBGT fan tripping in 10 minutes is a failed "black box" step on the ST. This means that one subsystem is inoperable. One inoperable subsystem requires that subsystem be returned to service within 7 days. Oistractors: A There is no recently irradiated fuel in the fuel pool because the unit has been on line for 300 days. Termination of fuel moves is not required. Plausible if the candidate does not recall the definition of "Recently Irradiated". B There is no recently irradiated fuel in the fuel pool because the unit has been on line for 300 days. Placing SBGT in-service as an option to continue fuel moves is not required. Plausible if the candidate does not recall the definition of "Recently Irradiated". c Placing the SBGT train in-service is only required after the 7 day window to return the system to service has expired. Plausible if the candidate does not understand the Tech Spec. PBS ILT 2015 CERT/NRC EXAM Page: 19 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109846 User-Defined ID: Cross Reference Number: 295017 2.2.12 Topic: ILT-5009A-14-001-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(2) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): Tech Spec, ST-0-09A-325-2 SBGT Subsystem Operability Test Learning PLOT-5009A-14 Objective: KIA System: 295017 High Off-Site Importance: Release Rate RO/SRO 3.7/4.1 KIA Statement: 2.2.12 - Knowledge of surveillance procedures. REQUIRED 1. Tech Spec section 3.6 (SBGT System) MATERIALS:
2. ST-0-09A-325-2, "SBGT Subsystem Operability Test" page 6 Notes and None Comments:
PBS ILT 2015 CERT/NRC EXAM Page: 20 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O 10 ID: 1110006 Points: 1.00 A automatic scram has occurred on Unit 3 due to a loss of Main Condenser vacuum. The following conditions exist:
  • Reactor power is 3% and steady
  • RPV level lowered to -35 inches and has recovered to -20 inches
  • Reactor Recirculation Pumps tripped on the Aux Bus fast transfer Based on the above conditions there is an entry condition for procedure _.....,U__,_1,_}_and the Crew is required to _(2)_.
A. (1) T-100 "Scram" (2) initiate Alternate Rod Insertion (ARI) using RRC 3B.1-3, "Alternate Rod Insertion During a Plant Event" B. (1) T-100 "Scram" (2) minimize CRD flow using SO 3.2.A-3, "Control Rod Drive Hydraulic System Shutdown" C. (1) T-101 "RPV Control" (2) initiate Alternate Rod Insertion (ARI) using RRC 3B.1-3, "Alternate Rod Insertion During a Plant Event" D. (1) T-101 "RPV Control" (2) inject Standby Liquid Control (SLC) using RRC 11.1-3, "Standby Liquid System Initiation During a Plant Event" Answer: A Answer Explanation Choice Basis or Justification Correct: A No entry condition to T-101 "RPV Control" exists (Reactor power is less than 4% and RPV level did not go below- 48 inches). Entry into procedure T-100 "Scram" is required. Because there is an ATWS (not all rods inserted) T-100 directs Alternate Rod Insertion (ARI) be initiated. Dis tractors: B CRD is needed for rod insertion. A prerequisite for use of the procedure is that all control rods are inserted. Plausible if the candidate does not recognize that CRD is needed to attempt rod insertion. c No entry for T-101 exits. Plausible if the candidate does not recall the T-101 entry conditions. The action to initiate ARI is also a plausible action with an ATWS. D No entry for T-101 exits. Plausible if the candidate does not recall the T-101 entry conditions. The action to inject SLC is also a plausible action with an ATWS. PBS ILT 2015 CERT/NRC EXAM Page: 21 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1110006 User-Defined ID: Cross Reference Number: 295015 2.1.23 Topic: ILT-2100-3-012-SRO Num Field 1: Num Field 2: Text Field: Comments: Psvchometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b )(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference( s): T-100, T-101 Learning PLOT-2100-3 Objective: KIA System: 295015 Incomplete Importance: SCRAM RO/SRO 4.3/ 4.4 KIA Statement: 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 22 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 11 ID: 1109868 Points: 1.00
  • Unit 2 is in MODE 2 with a reactor startup in progress
  • The reactor is subcritical
  • The 2B 24/48 VDC Distribution Panel (2BD045) is lost The loss of power to 2BD045 causes a control rod block (1) from the Wide Range Neutron Monitoring (WRNM) System. The Crew shall (2)
A. (1)0NLY (2) bypass the Rod Block signal using AO 60C.1-2 "Bypassing WRNM Control Rod Withdraw Block" and continue the startup B. (1)0NLY (2) suspend control rod withdrawal immediately per Technical Specifications C. (1) and RPS Channel 'B' Half Scram (2) bypass the Rod Block signal using AO 60C.1-2 "Bypassing WRNM Control Rod Withdraw Block" and the Half Scram signal using GP-11. E "RPS Scram and ARI Reset" and continue the startup D. (1) and RPS Channel 'B' Half Scram (2) suspend control rod withdrawal immediately per Technical Specifications Answer: D Answer Explanation Correct: D A loss of power to 200045 will result in a half scram and rod block due to a WRNM INOP condition caused by the loss of power to the 4 "B" channel WRNMs. With 4 WRNM channels INOP, Tech Specs required that control rod withdraw be suspended immediately. Dis tractors: A Plausible if applicant does not understand the effects of a power loss on the WRNM system and believes the given conditions will only result in a rod block and does not understand that power has been lost to 3 required WRNMs. The startup can not continue until three of the four INOP WRNMs can be returned to service. B Plausible if applicant does not understand the effects of a power loss on the WRNM system and believes the given conditions will only result in a rod block. c Plausible if applicant does not understand the effects of a power loss on the WRNM system and does not understand that power has been lost to 3 required WRNMs. The startup can not continue until three of the four INOP WRNMs can be returned to service. PBS ILT 2015 CERT/NRC EXAM Page: 23 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109868 User-Defined ID: IL T-5060C-2C-001 Cross Reference Number: 215004A2.01 Topic: IL T-5060C-2c-002-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: NRC-09-1 Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: New Exam item Previous NRC Exam XModified Bank Other Exam Bank IL T Exam Bank Reference(s): ARC-210 H-3, E-24, Learning PLOT-5060C-2 Objective: KIA System: 215004 Source Range Importance: Monitor (SRM) System RO/SRO 2.712.9 KIA Statement: A2.01 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 24 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 12 ID: 1118714 Points: 1.00 The following alarms are received:
  • 220 F-5, "INVERTER TROUBLE"
  • 220 G-5, "INVERTER DC SUPPLY UNDERVOLTAGE" Based on the above alarms, power will be (1} to Panel Y-50 "Uninterruptible 125 VAC Bus".
Enter and execute (2} A. (1) lost (2) ON-112, "Loss of Uninterruptible AC Power" to stabilize RPV level. B. (1) lost (2) SO 588.7.A-2, "Removing Unit 2 U.P.S. Static Inverter From Service" to provide power directly from the AC source until power to the static inverter is restored. C. ( 1) maintained (2) ON-112, "Loss of Uninterruptible AC Power" to stabilize RPV level. D. ( 1) maintained (2) SO 588.7.A-2, "Removing Unit 2 U.P.S. Static Inverter From Service" to provide power directly from the AC source until power to the static inverter is restored. Answer: D Answer Explanation Choice Basis or Justification Correct: D The static switch is a "make before break" contact therefore power will be maintained to Y-50 when the normal supply is lost. ARC 220-F-5 and 220G-5 provides an option to perform SO 588. 7.A to remove the static inverter from service at the discretion of Shift Management. Distractors: A Plausible if the candidate does not understand that the static switch will transfer on lowering DC voltage from the static inverter therefore maintaining power to Y-50. If the candidate believes that power will be lost to Y-50 then entry into ON-112 would be appropriate to stabilize RPV level. B Plausible if the candidate does not understand that the static switch will transfer on lowering DC voltage from the static inverter therefore maintaining power to Y-50. c A symptom for entry into ON-112 is alarm 220 F-5. With the transfer of power to the AC supply for Y-50 executing ON-112 to stabilize RPV level is not correct. Plausible if the candidate does not understand that ON procedure entry and execution without an actual loss of power to y-50 is not correct. PBS ILT 2015 CERT/NRG EXAM Page: 25 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1118714 User-Defined ID: Cross Reference Number: 262002A2.01 Topic: ILT-1550-1 ?b-003-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps 1chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): ARCs 220 F-5 & G-5, E-28, PLOT 5058 Learning PLOT-1550-17b Objective: KIA System: 262002 Uninterruptable Importance: Power Supply RO/SRO 2.6/ 2.8 KIA Statement: A2.01 - Ability to (a) predict the impacts of the following on the UNINTERRUPTIBLE POWER SUPPLY (A.C./D.C.) and (b) based on those prediction, use produces to correct, control, or mitigate the consequences of those abnormal conditions or operations: Under voltage REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 26 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 13 ID: 1119457 Points: 1.00 Unit 2 was operating at 100% power. The following conditions exist:
  • The "B" RHR loop is blocked and drained for repairs
  • A loss of Off-Site power occurs
  • The E-3 and E-4 Diesel Generators start and load their 4 KV buses
  • RPV level is 23 inches being maintained by RCIC
  • RPV pressure is 900 psig being maintained by HPCI in the CST-CST mode
  • Off-site power is not expected to be restored for several hours
  • A small steam leak occurs on Unit 2 requiring the use of containment sprays Using the attached table select the correct statement with respect to the loss of Off-Site power.
I REVIEW THE PURPOSE AND PREREQUISITES OF THE APPLICABLE BACKFEED ATTACHMENT: DIG COMBINATION ATTACHMENT EI & E2 AVAILABLE *********************. D EI & E3 AV AIL ABLE ...................... E EI & E4 AVAILABLE ...................... F E2 & E3 AVAILABLE ..*..****.****.**...* G E2 & E4 AVAILABLE ..................... H E3 & E4 AVAILABLE ***.****.**********.. J L C I 5 I I A. Backfeed is not required, spray Containment using T-204-2, "Initiation of Containment Sprays Using RHR". B. Backfeed is required using Attachment J, "Backfeeding Safe Shutdown Loads With the E3 & E4 Diesel Generators Available". C. Backfeed is required using Attachment P, "Generic Load Management Contingency During Loop Events". D. Secure D/Gs using Attachment A, "Diesel Generator Lockout From the Main Control Room" until backfeed is available to E-22 bus to provide D/G cooling. Answer: B PBS ILT 2015 CERT/NRG EXAM Page: 27 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRG Senior Reactor Operator Exam - Revision 0 Answer Explanation Choice Basis or Justification Correct: c Power is not available to perform Containment Sprays and provide injection without performing a backfeed. Direction to implement the backfeed attachment is given by Shift Management. Distractors: A Plausible if the candidate does not recognize the backfeed attachment needs to be performed because there is not sufficient power available to spray containment.. B Plausible if the candidate does not recognize that the normal back feed attachment is sufficient to restore power to containment spray valves. D Plausible if the candidate does not understand the power supplies to the ESW and ECW pumps. With power to the E3 and E4 D/Gs cooling water is available to the D/Gs. Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1119457 User-Defined ID: Cross Reference Number: 264000 2.4.11 Topic: ILT-1555-3-023-SRO Num Field 1: 2015 NRG Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: XNew Exam item Previous NRG Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): SE-11 Learning PLOT 1555-3 Objective: KIA System: 264000 Emergency Importance: Generators RO/SRO 4.0/ 4.2 KIA Statement: 2.4.11 Knowledge of abnormal condition procedures. PBS ILT 2015 CERT/NRC EXAM Page: 28 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 29 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 14 ID: 1110320 Points: 1.00
  • Unit 3 is at 100% power
  • EHC load set is at 105%.
Based on the above conditions, Main Turbine control valves will (1) Direct the operator to (2} A. (1) close for 94% flow demand (2) cycle the SRV control switch per OT-114 "Inadvertent Opening of a Relief Valve" B. (1) close for 94% flow demand (2) scram the Reactor when Main Steam Line pressure approaches 880 psig per OT-111 "Reactor Low Pressure" C. (1) remain at 100% flow demand (2) cycle the SRV control switch per OT-114 "Inadvertent Opening of a Relief Valve" D. (1) remain at 100% flow demand (2) scram the Reactor when Main Steam Line pressure approaches 880 psig per OT-111 "Reactor Low Pressure" Answer: A Answer Explanation Choice Basis or Justification Correct: A Output of pressure regulator lowers sending a lower signal to control valve demand. As control valves close (-6%) reactor pressure will remain constant offsetting the SRV being open. Since RPV pressure does not change OT-114 is the only procedure required to be entered. At the SRO's discretion the SRV control switch is cycled. Distractors: B Plausible if the candidate does not understand how the pressure set section of EHC functions to control RPV pressure and believes that RPV pressure will lower. If pressure is lowering OT-111 "Reactor Low Pressure" would be entered. OT-111 would direct scraming if MSL pressure approaches 880 psig. Plausible if the candidate believes that RPV pressure would drop. c Plausible if the candidate does not understand how the pressure set section of EHC functions to control RPV pressure and believes that RPV pressure will not lower. Since RPV pressure does not change OT-114 is the only procedure required to be entered. At the SRO's discretion the SRV control switch is cycled. D Plausible if the candidate does not understand how the pressure set section of EHC functions to control RPV pressure and believes that RPV pressure will lower. If pressure is lowering OT-111 "Reactor Low Pressure" would be entered. OT-111 would direct scraming if MSL pressure approaches 880 psig. Plausible if the candidate believes that RPV pressure would drop. PBS ILT 2015 CERT/NRG EXAM Page: 30 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1110320 User-Defined ID: ILT-5001 DL-6E-001 Cross Reference Number: 241000 2.1.7 Topic: ILT-5001 DL-7e-002-SRO SRV Fails open I EHC response Num Field 1: 2015 Num Field 2: N/A Text Field: A Comments: Ps 1chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: New Exam item Previous NRC Exam XModified Bank Other Exam Bank ILT Exam Bank Reference(s): PLOT 5001 DL, OT-114 Learning PLOT-5001 DL-7e Objective: KIA System: 241000 Reactor/Turbine Importance: Pressure Regulating RO/SRO System 4.4/ 4.7 KIA Statement: 2.1. 7 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 31 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O 15 ID: 1120226 Points: 1.00
  • Unit 2 is at 100% power
  • RPV level is +23 inches and stable
  • Digital Feedwater Control System (DFCS) is in three element control Based on the above, which of the following describes the plant response to a loss of fill feedwater flow signals to the DFCS?
When CONDITIONS STABILIZE, the Crew shall _ _ A. maintain RFP suction pressure above 340 psig per OT-100, "Reactor Low Level" due to the RFP min flow valves failing open B. monitor for THI per OT-112, "Unexpected Unexplained Change in Core Flow" due to a 30% runback C. monitor for THI per OT-112, "Unexpected Unexplained Change in Core Flow" due to a 45% runback D. trip a RFP to maintain RPV level below the Main Steam Lines per OT-110, "Reactor High Level" Answer: B Answer Explanation Choice Basis or Justification Correct: B The loss of the Total Feedwater input will cause a 30% reactor recirculation system runback transient. OT-112 is required to be entered due to the recirc runback resulting in reduced reactor core flow. One of the early follow-up actions of OT-112 is to monitor for Thermal Hydraulic Instability. Distractors: A Maintaining Reactor Feed Pump (RFP) suction pressure above 340 psig by limiting Reactor power in accordance with GP-9-2 "Fast Reactor Power Reduction" is a follow-up action out of OT-100 for low RPV water level. At no time will RPV level go low during due to the 30% reactor recirculation run back. Plausible if the candidate does not understand how the feedwater input affects the feedwater control system. c The loss of the Total Feedwater input will cause a 30% reactor recirculation system runback transient. OT-112 is required to be entered due to the recirc runback resulting in reduced reactor core flow. One of the early follow-up actions of OT-112 is to monitor for Thermal Hydraulic Instability. Plausible if the candidate does not understand that a total loss of Feedwater signals will case a 30% runback and not a 45% runback. PBS ILT 2015 CERT/NRG EXAM Page: 32 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 D Tripping a RFP could be a follow-up action from procedure OT-110 "Reactor High Level". Reactor level will initially rise during the Reactor Recirculation Pump run back, but the RFPs will respond to maintain RPV level back to normal. If the candidate does not understand that level control automatic swaps to single element, then it is reasonable to assume that with a lower feed flow signal the feed pumps would speed up and RPV level would be above 23 inches. Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1120226 User-Defined ID: Cross Reference Number: 259002 A2.02 Topic: IL T 5006-6a-006-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps*1chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 10 CFR 55.43(b) (5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference( s): PLOT - 5006 Learning PLOT - 5006-6a Objective: KIA System: 259002 - Reactor Water Importance: Level Control System RO/SRO 3.3/ 3.4 KIA Statement: A2.02 - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of any number of reactor feedwater flow inputs REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 33 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 16 ID: 1109486 Points: 1.00 Unit 2 Traversing In-Core Probe (TIP) System operation is in progress for an LPRM calibration. A subsequent Feedwater transient results in the following conditions:
  • The Reactor was manually scrammed
  • RPV level lowered to -10 inches and is now at +20 inches
  • The PRO reports the in-service TIP detector is driving into the core and the ball valve RED light is lit.
Based on the above conditions, determine the required initial action (if any). A. Direct the Reactor Engineer to continue the TIP trace IAW RE-35-2 'TIP System Operation." B. No operator actions are required per GP-8.B, "PCIS Isolations - Groups II and Ill. C. Direct the PRO to manually withdraw the TIP detector and close the ball valve IAW SO 7F.7-A-2 "TIP System Isolation in Event of Containment Isolation." D. Direct the PRO to manually fire the shear valve IAW SO 7F.7-A-2 "TIP System Isolation in Event of Containment Isolation." Answer: C Answer Explanation Choice Basis or Justification Correct: c For a TIP failure to isolate, GP-8.B directs manual isolation IAW SO 7F.7-2, which directs manually withdrawing the TIP detector to shield and closing the ball valve. This is recent plant OE. There was a concern about what the correct action was. SO 7F. 7-2 now clearly lists the order to take the actions attempt to withdraw before firing the shear valve. Distractors: A The TIP detector should automatically withdraw to shield and the ball valve should automatically close at 1-inch RPV level. Plausible if the candidate does not recall the isolation signal or the expected response to an isolation signal. Continuing to insert a TIP with a failed isolation signal is not correct. B GP-8.B will direct the actions to take with a failed isolation. Plausible if the candidate does not understand the requirements following an isolation signal. D The shear valve is only fired if the detector can not be retracted and then only if directed by the Shift Manager. Plausible if the candidate does not understand the requirements following an isolation signal. PBS ILT 2015 CERT/NRG EXAM Page: 34 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109486 User-Defined ID: Cross Reference Number: 215001A2.08 Topic: ILT-5007F-7d-002-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psvchometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): GP-8.B, SO 7F.7.A-2 Learning PLOT-5007F-7d Objective: KJA System: 215001 Traversing In- Importance: Core Probe RO/SRO 2.712.9 KJA Statement: A2.08 - Ability to (a) predict the impacts of the following on the TRAVERSING IN-CORE PROBE and (b) based on those prediction, use produces to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to retract to shield REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 35 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 17 ID: 1110029 Points: 1.00 The following plant conditions exist on Unit 3:
  • Reactor power is stable at 93% following a transient.
  • 'A' Recirc pump speed is 65%.
  • 'B' Recirc pump speed is 82%.
  • 'A' jet pump loop flow is 37.80 Mlbm/hr.
  • 'B' jet pump loop flow is 49.50 Mlbm/hr.
Based on the above conditions, determine which, if any, action is required by Technical Specifications and the associated bases. A. No action is required at this time. Core cooling is assured if a LOCA where to occur at these pump speeds. B. Immediately trip the 'A' RRP, enter "Single Loop" operations and apply thermal limit penalties within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Core cooling may not be met if a LOCA were to occur during the time when pump speeds are mismatched. C. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> raise "A' RRP speed to match loop flows within ~ 10.25 Mlbm/hr. This reduces the vibration on the jet pumps with the low flow condition. D. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> lower 'B' RRP speed to match loop flows within~ 5.125 Mlbm/hr. Core cooling may not be met if a LOCA were to occur during the time when pump speeds are mismatched. Answer: D Answer Explanation I Choice Basis or Justification Correct: D Technical Specification (TS) 3.4.1 requires loop flows to match within~ 5.125 Mlbm/hr. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> since total core flow will be greater than 71.75 Mlbm/hr after lowering the B RRP flow to match the A RRP. Per TS bases core cooling may not be met if a LOCA were to occur during the time when pump speeds are mismatched. Distractors: A Incorrect. Actiion is required by TS 3.4.1 since the RRP loop flows are not matched. Per TS bases core cooling may not be met if a LOCA were to occur during the time when pump speeds are mismatched. B Incorrect. There is no procedural or TS guidance to trip the lower speed pump and intentionlly enter single loop operation. Plausible if the Candidate misinterrprets TS 3.4.1 guidance if the unit was already in single loop operation. PBS ILT 2015 CERT/NRC EXAM Page: 36 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 c Incorrect. There is no guuidance to raise the "A' RRP speed to match loop flows since this is the pump that is locked up and caused the loop flow mismatch in the first place. Also, getting the loop flows within~ 10.25 Mlbm/hr is the TS requirement if total core flow was < 71. 75 Mlbm/hr. Not the case here. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time frame is related to the TS 3.4.1 required limit modifications for single recirculation loop operation. It may be delayed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single recirculation loop operation. Not the case here. Both loop of RRP stay in operation. Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1110029 User-Defined ID: A-ILT-5002-8-003 Cross Reference Number: 202002 G2.2.40 Topic: ILT-5002-14-007-SRO Num Field 1: 2015 NRC Num Field 2: 0.00 Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(2) Source Documentation Source: New Exam item Previous NRC Exam XModified Bank Other Exam Bank ILT Exam Bank Reference(s): OT-112, Tech Spec 3.4.1 and Bases Learning PLOT-5002-14 Objective: KIA System: 202002 Recirculation Importance: Flow Control System RO/SRO 3.4/ 4.7 KIA Statement: 2.2.40 Ability to apply Technical Specification for a system. REQUIRED Tech.Spec. Section 3.4 MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 37 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 18 ID: 1110187 Points: 1.00
  • A fuel bundle is being moved in the Unit 2 fuel pool.
  • It is currently on the fuel hoist and moving to a new location in the pool.
  • During the move Fuel Pool level lowers to 232 feet and is continuing to lower.
Complete the statements below with respect to a fuel handling accident, and the required action for the lowering Fuel Pool level. The US FAR _ _.(_,,1),__ release limit may not be maintained for a Fuel Handling Accident. Based on the above conditions, Technical Specifications requires .(2.) A. (1) iodine (2) immediately stop moving the fuel bundle, leave the fuel bundle on the hoist until Fuel Pool level is recovered. B. (1)iodine (2) completing the fuel move and suspending all subsequent moves until Fuel Pool level is recovered. C. (1) noble gas (2) immediately stop moving the fuel bundle, leave the fuel bundle on the hoist until Fuel Pool level is recovered. D. (1) noble gas (2) completing the fuel move and suspending all subsequent moves until Fuel Pool level is recovered. Answer: B Answer Explanation Choice Basis or Justification Correct: B When Fuel Pool level drops below 232 feet 3 inches Technical Specifications requires "Suspend movement of fuel assemblies in the spent fuel storage pool immediately. The bases goes on to explain that in this case the bundle movement shall continue to a safe position/location. Distractors: A Plausible if the candidate does understand that leaving the bundle suspended is not in a safe location and that the bases requires that the move be completed to put the bundle in a safe location. c Plausible if the candidate is not familiar with the bases for the water in the fuel pool providing a Iodine decontamination factor. Noble gases are not water soluable. Plausible if the candidate does understand that leaving the bundle suspended is not in a safe location and that the bases requires that the move be completed to put the bundle in a safe location. D Plausible if the candidate is not familiar with the bases for the water in the fuel pool providing a Iodine decontamination factor. Noble gases are not water soluable. PBS ILT 2015 CERT/NRC EXAM Page: 38 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1110187 User-Defined ID: Cross Reference Number: 233000 2.2.22 Topic: ILT-5019-14-001-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps *chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b )(2) Source Documentation Source: XNew Exam item Previous N RC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): Tech Spec 3.7.7 and Bases Learning PLOT-5019-14 Objective: KIA System: 233000 Fuel Pool Cooling Importance: and Cleanup RO/SRO 4.0/ 4.7 KIA Statement: 2.2.22 Knowledge of limiting conditions for operations and safety limits. REQUIRED Technical Specification section 3.7 MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 39 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 19 ID: 1120466 Points: 1.00 A Refuel Outage is in progress on Unit 2. The following conditions exist:
  • The 50th fuel bundle from the Core Component Transfer Authorization Sheet (CCTAS) is being lowered into the core.
  • All WRNM detectors have at least five (5) fuel bundles adjacent to the detectors.
  • WRNM count rate doubles two times as the bundle is lowered into the core.
With respect to the above conditions what action is required per FH-6C, "Core Component Movement - Core Transfers"? A Complete lowering the bundle into the core then continue with the next schedule bundle move. B. Complete lowering the fuel bundle into the core, then suspend fuel movements. C. Raise the bundle from the core so that it clears the upper grid. D. Return the bundle to the fuel pool. Answer: C Answer Explanation Choice Basis or Justification Correct: c Procedure FH-6C and ON-124 directs that if count rate doubles two times that the bundle shall be raised above the upper grid. Distractors: A Plausible if the candidate is not familiar with the requirements of FH-6C. If count rate had only doubled one time then placing the bundle would be the correct answer. B Plausible if the candidate is not familiar with the requirements of FH-6C. If count rate had only doubled one time then placing the bundle would be the correct answer. D Plausible if the candidate is not familiar with the requirements of FH-6C. PBS ILT 2015 CERT/NRG EXAM Page: 40 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficu ltv: 0.00 System ID: 1120466 User-Defined ID: NLSR0-0763-3-002 Cross Reference Number: 234000 K3.03/2.1.41 Topic: ILT-0763-3-003-SRO Num Field 1: 2015 NRC Num Field 2: N/A Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.43(b)(7) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference( s ): FH-6 Learning NLSR0-0760-3 Objective: KIA System: 2.1 Conduct of Operations Importance: RO/SRO 2.8/ 3.7 KIA Statement: 2.1.41 - Knowledge of the refueling process. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 41 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 20 ID: 1109527 Points: 1.00 A break occurs in the instrument air supply line to A0-9120A. Using P&ID M-304 sheet 2, determine the impact on feedwater heating and what action is required. Feedwater heating _ _.(-'-1,_)_lost, and the Crew shall _(2)_. A. (1)is (2) return Reactor power to the pre-transient level. B. (1)is (2) reduce Reactor power 10% below the pre-transient level. C. (1)isnot (2) place the Backup Air compressor in-service. D. (1) is not (2) cross tie the Unit 2 and Unit 3 air headers. Answer: A Answer Explanation Choice Basis or Justification Correct: A The loss of air causes the A0-9120A to fail closed as determined on print M-304 Sheet 2. The closed valve will isolate extraction steam to the A4 feedwater heater thereby lowering feedwater temperature and raising reactor power. OT-104 "Positive Reactivity Insertion" must be entered. OT-104 states: IF only one feedwater heater is out of service/isolated after the transient AND all 5th stage feedwater heaters are in service, THEN INSERT control rods as necessary to maintain APRM indicated power within the analyzed region of the Power Flow Map AND less than or equal to the pre-transient power level. Distractors: B Incorrect. OT-104 states to MAINTAIN power at least 10% below the initial level IF the cause of the positive reactivity insertion CANNOT be determined. Not the case here. c The loss of air causes the A0-9120A to fail closed as determined on print M-304 Sheet 2. The closed valve will isolate extraction steam to the A4 feedwater heater thereby lowering feedwater temperature and raising reactor power. ON-119 "Loss of Instrument Air" would only be entered if the unit instrument air pressure/supply were threatened (low system pressure). A single instrument air line break is not beyond the capacity of the system and is not enough to effect the overall instrument air system pressure and therefore entry into ON-119 is not required here. PBS ILT 2015 CERT/NRG EXAM Page: 42 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 D The loss of air causes the A0-9120A to fail closed as determined on print M-304 Sheet 2. The closed valve will isolate extraction steam to the A4 feedwater heater thereby lowering feedwater temperature and raising reactor power. ON-119 "Loss of Instrument Air" would only be entered if the unit instrument air pressure/supply were threatened (low system pressure). A single instrument air line break is not beyond the capacity of the system and is not enough to effect the overall instrument air system pressure and therefore entry into ON-119 is not required here. Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109527 User-Defined ID: Cross Reference Number: 2.2.15 Tooic: ILT1540-7-001-SRO-OT-104 Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b )(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank IL T Exam Bank Reference(s): OT-104 Learning PLOT-1540-7 Objective: KIA System: 2.2 Equipment Control Importance: RO/SRO 3.9/ 4.3 KIA Statement: 2.2.15 - Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. REQUIRED M-304 Sheet 2 MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 43 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRG Senior Reactor Operator Exam - Revision 0 21 ID: 994801 Points: 1.00 A transient on Unit 2 resulted in the following conditions:
  • Containment venting is required for combustible gas control using T-200-2 "Primary Containment Venting"
  • Chemistry determined that the maximum Containment vent rate that will not exceed the General Emergency release rate is 2,000 scfm
  • Drywell pressure on PR-2508 is 25 psig
  • Standby Gas Treatment is available Using Figure 1 of T-200-2, PROVIDED BELOW, determine which one of the following vent paths will most quickly remove the combustible gases without exceeding the General Emergency release rate.
FIGURE 1 MAXIMUM PRIMARY CONTAINMENT VENT RATE FOR VARIOUS VENT PATH SIZES Maximum vent Path Volumetric Flowrate 1.COO,OGC -18inchVe"*:to SBGTS 108.000 100,000 cfm ~ u.. ~ ...,...16 in:h Torus
e. 10.00G Hi.lrdered Ve*1:
a:: ~: 79,000 cfm 0 Li: CJ
  • c: 1,000 I - 6 inch iLRT Line
'5 2BOO cfm E 0 iOO I -+-2 inch Har*:! Vent toSSGTS 311 cfm 10 0 10 20 30 40 50 EO 70 80 90 10:J 11D Containment Pressure (psig) A. 2 inch hard vent to SBGTS B. 6 inch ILRT line C. 16 inch Torus Hardened Vent D. 18 inch vent to SBGTS Answer: A PBS ILT 2015 CERT/NRC EXAM Page: 44 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Answer Explanation Correct: A Plot Containment pressure of 25 psig and vent rate of 2000 SFCM, the point is ABOVE the 2 in Hard Vent to SBGTS Line and BELOW the 6 inch ILRT Line; the 2 in Hard Vent to SBGTS is the largest vent path that will NOT exceed the GE release rate. Distractors: B Plot Containment pressure of 25 psig and vent rate of 2000 SFCM, the point is ABOVE the 2 in Hard Vent to SBGTS Line and BELOW the 6 inch ILRT Line; the 2 in Hard Vent to SBGTS is the largest vent path that will NOT exceed the GE release rate. Plausible if plotted wrong or the candidate does not understand the curve. c Plot Containment pressure of 25 psig and vent rate of 2000 SFCM, the point is ABOVE the 2 in Hard Vent to SBGTS Line and BELOW the 6 inch ILRT Line; the 2 in Hard Vent to SBGTS is the largest vent path that will NOT exceed the GE release rate. Plausible if plotted wrong or the candidate does not understand the curve. D Plot Containment pressure of 25 psig and vent rate of 2000 SFCM, the point is ABOVE the 2 in Hard Vent to SBGTS Line and BELOW the 6 inch ILRT Line; the 2 in Hard Vent to SBGTS is the largest vent path that will NOT exceed the GE release rate. Plausible if plotted wrong or the candidate does not understand the curve. Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 994801 User-Defined ID: IL T-2102-7B-004 Cross Reference Number: G.2.3 G.2.3.11 ILT-2102-7B-004 A transient on Unit 2 resulted in the following Topic: conditions: *Containment ventinq is Num Field 1: Num Field 2: Text Field: NRC-09-1 Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(4) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XILT Exam Bank Reference(s): T-102 and bases, T-200-2 PBS ILT 2015 CERT/NRC EXAM Page: 45 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O Learning PLOT-2102-?b Objective: KIA System: 2.3 Radiation Control Importance: RO/SRO 3.8/ 4.3 KIA Statement: 2.3.11 - Ability to control radiation releases REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 46 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 22 ID: 1109652 Points: 1.00 A high power ATWS has occurred on Unit 2. The following conditions exist:
  • RPV pressure is rapidly fluctuating between 1130 and 1135 psig
  • Reactor power is fluctuating between 55 and 65%
  • The "C" SRV is CYCLING
  • Instrument nitrogen has not been restored Based on the above conditions, which of the below statements is the highest priority action?
A. Stabilize RPV pressure at 1050 psig to minimize Torus heatup using procedure RRC 1G.2-2 "Relief Valve Manual Operation During a Plant Event". B. Reduce RPV pressure below 950 psig to prevent SRV tailpipe failure using procedure RRC 1G.2-2 "Relief Valve Manual Operation During a Plant Event". C. Restore Instrument Nitrogen using RRC 16.1-2 "Bypass and Restore Instrument Nitrogen Supply to the Drywell", then stabilize RPV pressure at 1050 psig to minimize Torus heatup. D. Restore Instrument Nitrogen using RRC 16.1-2 "Bypass and Restore Instrument Nitrogen Supply to the Drywell", then reduce RPV pressure below 950 psig to prevent SRV tailpipe failure. Answer: B Answer Explanation Choice Basis or Justification Correct: B The information given in the stem of the question indicates that the "C" SRV is cycling. T-101 bases states; "Cycling SRVs pose several potential challenges to plant operation for the following reasons. One is the significant dynamic load imposed on the RPV, SRV tailpipes and supporting structures, and the Primary Containment". T-101 directs that if there is a cycling SRV to reduce RPV pressure to 950 psig regardless of the Status on Instrument Nitrogen. Distractors: A Minimizing Torus heatup in not a bases step for stabilizing RPV pressure. If a SRV is not cycling then Instrument Nitrogen is restored before pressure control is established. Plausible if the candidate does not diagnosis the cycling SRV and implements the standard pressure control step to stabilize pressure below 1050 psig. c Minimizing Torus heatup in not a bases step for stabilizing RPV pressure. Plausible if the candidate does not diagnosis the cycling SRV and implements the standard pressure control step os stabilize pressure below 1050 psig. D Plausible if the candidate does not recall that establishing pressure control when an SRV is cycling has priority over restoring Instrument Nitrogen. PBS ILT 2015 CERT/NRG EXAM Page: 47 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109652 User-Defined ID: Cross Reference Number: 2.4.18 Topic: ILT-2101-6-004-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b)(5) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): T-101 BASES Learning PLOT-2101-6 Objective: KJA System: 2.4 Emergency Importance: Procedures I Plan RO/SRO 3.3/ 4.0 KJA Statement: 2.4. 18 Knowledge of the specific bases for EOPs REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 48 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 23 ID: 994327 Points: 1.00
  • Unit 2 is being shutdown for a refueling outage in accordance with procedure GP-3-2, "Normal Plant Shutdown"
  • The initial Drywell entry is being prepared in accordance with procedure RP-PB-461, "Drywell Initial Entry" To protect personnel making the Drywell entry from unneccessary radiation exposure, procedures GP-3-2 and RP-PB-461 require that Operations personnel apply a(n) (1)_ to the Traversing In-core Probe (TIP) System controls.
RP-PB-461 also requires Drywell entry approval from both a Radiation Protection Supervisor and from (2) A. (1) Clearance (2) the Plant Manager B. (1) Clearance (2) Operations Shift Management C. (1) Equipment Status Tag (2) Operations Shift Management D. ( 1) Equipment Status Tag (2) the Plant Manager Answer: B Answer Explanation Choice Basis or Justification Correct: B Per GP-3-2 (Rev.1, step 6. 76) and RP-PB-461, Attachment 1 -Initial Entry Checklist, Operations personnel must apply a clearance to the Traversing In-core Probe (TIP) System controls in order to ensure that TIPS are not run and in their shields to protect personnel from any accidental radiation exposure. RP-PB-461, Attachment 1, also requires Drywell entry approval from both a Radiation Protection Supervisor and from Operations Shift Management. Distractors: A The management level of approval in incorrect. RP-PB-461, Attachment 1, requires Drywell entry approval from both a Radiation Protection Supervisor and from Operations Shift Management. c Incorrect. An Equipment Status Tag is not an acceptable process for protecting station personnel. Per GP-3-2 (Rev.1, step 6.76) and RP-PB-461, Attachment 1 - Initial Entry Checklist, Operations personnel must apply a clearance to the Traversing In-core Probe (TIP) System controls in order to ensure that TIPS are not run and in their shields to protect personnel from any accidental radiation exposure. PBS ILT 2015 CERT/NRC EXAM Page: 49 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 D Both parts are incorrect. An Equipment Status Tag is not an acceptable process for protecting station personnel. Per GP-3-2 (Rev.1, step 6.76) and RP-PB-461, Attachment 1 -Initial Entry Checklist, Operations personnel must apply a clearance to the Traversing In-core Probe (TIP) System controls in order to ensure that TIPS are not run and in their shields to protect personnel from any accidental radiation exposure. RP-PB-461, Attachment 1, requires Drywell entry approval from both a Radiation Protection Supervisor and from Operations Shift Management. Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994327 User-Defined ID: ILT-1730-2C-001 Cross Reference Number: G2.3.13 Topic: ILT-1730-2c-001 Drywell Initial Entry Num Field 1: 0.00 Num Field 2: 0.00 Text Field: ILT05-1 NRC Exam SR0#23 Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes) MEMORY 1OCRF55.43(b)(4) Source Documentation Source: XNew Exam item Previous NRC Exam Modified Bank Other Exam Bank ILT Exam Bank Reference(s): GP-3-2; RP-PB-461 Learning PLOT-1730-2c Objective: KIA System: 2.3 Radiation Control Importance: RO/SRO 3.4/ 3.8 KIA 2.3.13- Knowledge of radiological safety Statement: 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. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 50 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 24 ID: 994196 Points: 1.00 A plant start-up and heat-up is in progress on Unit 3 with both recirc pumps in service. Reactor power is 5%. The following data has been collected: RPV DRAIN TEMP "A" RECIRC LOOP TEMP "B" RECIRC LOOP TEMP 0915 221 degrees 250 degrees 252 degrees 0930 250 degrees 275 degrees 278 degrees 0945 275 degrees 305 degrees 308 degrees 1000 310 degrees 335 degrees 337 degrees 1015 319 degrees 349 degrees 364 degrees Based on the above data, which one of the following describes the required actions? A Additional control rods may be withdrawn in accordance with the NF-AB-720 approved sequence. Rods must be moved by single notch withdrawal. B. Insert control rods in the reverse order of the NF-AB-720 approved sequence and take Technical Specification actions. C. Additional control rods may be withdrawn in accordance with the NF-AB-720 approved sequence. Rods can be withdrawn using continuous withdraw. D. Insert control rods in accordance with GP-9-3, "Fast Reactor Power Reduction". Answer: B Answer Explanation Choice Basis or Justification Correct: B Heatup rate is in excess of the 100°F/hour TS limit (B Recirc loop delta temperature from 09: 15 to 10: 15 = 112 F) GP-2 requires the operator to insert control rods in reverse order of the NF-AB-720 approved sequence. Distractors: A It is NOT within the TS limit, and is outside of the administrative heat up rate defined in GP-2. (90°F). Plausible if the candidate does not calculate the values correctly or does not understand the requirements of exceeding the heatup rate. c Heatup rate is not within admin limit. Plausible if the candidate does not calculate the values correctly or does not understand the requirements of exceeding the heatup rate. D While heatup rate is outside the 90°F/hr limit, rods would not be driven in via GP-9-3. Plausible if the candidate does not calculate the values correctly or does not understand the requirements of exceeding the heatup rate. PBS ILT 2015 CERT/NRC EXAM Page: 51 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 994196 User-Defined ID: A-IL T-1530-4-001 Cross Reference Number: 290002 G 2.1.7/2.1.25 IL T-1530-4-002-SRO A plant start-up and heat-up is in progress on Topic: Unit 3 with both recirc pumps in Num Field 1: 2015 NRC Num Field 2: 0.00 Text Field: Comments: Psvchometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b )(5) Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Other Exam Bank XIL T Exam Bank Reference(s): GP-2, ST-0-080-500-3 Learning PLOT 1530-4 Objective: KIA System: 2.1 Conduct of Importance: Operations RO/SRO 3.9/ 4.2 KIA Statement: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRC EXAM Page: 52 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision 0 25 ID: 1109654 Points: 1.00 The following conditions exist on Unit 2 following a loss of all condensate pumps:
  • HPCI is blocked for maintenance
  • RCIC is controlling RPV level between -70 and -100 inches
  • RCIC turbine malfunction results in exhaust pressure rising to 12 psid
  • Exhaust rupture discs PSD-3 and PSD-4 rupture as designed
  • All Low Pressure ECCS pumps are available ARC 222 E-2, "RCIC TURB EXH DIAPHRAGM HI PRESS, (OPERATOR ACTIONS) contains the following statement:
lE not required for adequate core cooling, THEN trip RCIC turbine. For the above conditions, the Crew can verify the rupture disc failure by verifying a rise in (1) RCIC shall (2) A. (1) Torus compartment temperature on point 8 of TR-2-13-139, "Area Temp" (2) remain in service in accordance with T-101, "RPV Control" to maintain ACC B. (1) Torus compartment temperature on point 8 of TR-2-13-139, "Area Temp" (2) be secured using RRC 13.1-2, "RCIC System Operation During a Plant Event" C. (1) Reactor Building Floor Drain Sump level as indicated by ARC-215 E-2, "RB Floor Drain Sump Hi-Hi-level". (2) be secured using RRC 13.1-2, "RCIC System Operation During a Plant Event". D. (1) Reactor Building Floor Drain Sump level as indicated by ARC-215 E-2, "RB Floor Drain Sump Hi-Hi-level". (2) remain in service in accordance with T-101, "RPV Control" to maintain ACC Answer: B Answer Explanation Choice Basis or Justification Correct: B RCIC Exhaust Rupture diaphragm vents to the Torus compartment. There are several options that need to be evaluated by the SRO before securing RCIC. There are other high pressure systems (CRD & SLC) that should be placed in-service to maintain RPV level. Low pressure ECCS is available if level does drop to -172 inches. RCIC operation is affecting plant parameters. Based on this information the SRO should determine that RCIC should be removed from service. Distractors: A Plausible if the candidate fails to recognize that RCIC is not required to maintain ACC. PBS ILT 2015 CERT/NRG EXAM Page: 53 of 54 03 February 2015 EXAMINATION ANSWER KEY 2015 NRC Senior Reactor Operator Exam - Revision O c Plausible if the candidate does not recall that the Rupture diaphragm discharges into the Torus Compartment and not the Reactor Building Sump Room. D Plausible if the candidate does not recall that the Rupture diaphragm discharges into the Torus Compartment and not the Reactor Building Sump Room. Plausible if the candidate fails to recognize that RCIC is not required to maintain ACC. Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 1.00 System ID: 1109654 User-Defined ID: Cross Reference Number: 2.4.50 Topic: ILT5013-1 Om-001-SRO Num Field 1: 2015 NRC Num Field 2: Text Field: Comments: Ps*1chometrics Level of Difficulty Time RO Knowledge Allowance (minutes) HIGH 1OCRF55.43(b )(5) Source Documentation Source: New Exam item Previous NRC Exam XModified Bank Other Exam Bank IL T Exam Bank Reference(s): ARC-222 E-2, T-101 Learning PLOT-5013-10m Objective: KIA System: 2.4 Emergency Importance: Procedures I Plan RO/SRO 4.2/ 4.0 KIA Statement: 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. REQUIRED None MATERIALS: Notes and None Comments: PBS ILT 2015 CERT/NRG EXAM Page: 54 of 54 03 February 2015
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