ML092940488

Ro/Sro August 2009 Written Exam

ML092940488
Person / Time
Site:	Clinton
Issue date:	10/22/2009
From:	Division of Nuclear Materials Safety III
To:	Exelon Generation Co, Exelon Nuclear
References
50-461/09-301, ILT 08-01
Download: ML092940488 (209)

Text

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 1 Question No:

ILT-7061 STA_Question RO Question SRO Question

a. Reference Provided:

Reference:

None 4100.02, CORE STABILITY CONTROL Explanation:

A. is correct, 4100.02, CORE STABILITY CONTROL requires a Reactor Scram if Core instabilities are observed.

B. is incorrect, restarting the RR pump would raise flow and may suppress the instabilities but is not allowed.

C. is incorrect, reducing power is correct if no instabilities are observed.

D. is incorrect, correct actions if no instabilities are observed.

System No:

KA No: RO: SRO: 295001 AA1.02 3.3 3.3 System/Evolution:

Partial or Complete Loss of Forced Core Flow Circulation Category Statement:

Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

K/A Statement:

RPS Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.7 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 2 Question No:

ILT-7074 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None EOP-1A, ATWS RPV Control R 28 Explanation:

B is correct with the ATWS a cooldown can only be commenced when either cold shutdown boron weight has been injected or the reactor is subcritical with no boron injected. In the stem SLC was started at 10:05. At 10:45 both SLC pumps have been operating for 40 minutes which corresponds to Cold Shutdown Boron Weight.

A is incorrect even if the reactor becomes subcritical, boron has been injected and therefore a cooldown cannot commence until cold shutdown boron weight has been injected IAW EOP-1A pressure leg.

C is incorrect this time relates to only 1 SLC pump running.

D is incorrect, the cooldown may commence before all rods are in if cold shutdown boron weight is injected.

System No:

KA No: RO: SRO: 295037 EK1.05 3.4 3.6 System/Evolution:

SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown Category Statement:

Knowledge of the operational implications of the following concepts as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

K/A Statement:

Cold shutdown boron weight: Plant-Specific Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.8 to 41.10

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 3 Question No:

ILT-7075 STA_Question RO Question SRO Question A Reference Provided:

Reference:

EOP-9 EOP-9, Radioactive Release Control R 28 Explanation:

A. is correct, EOP-9 requires restarting Turbine Building Ventilation to prevent an unmonitored release.

B. is incorrect, restarting ventilation will lower the radiation levels in the Turbine Building, but will NOT reduce the radioactive release due to filtration.

C. is incorrect, maintaining ventilation tripped would make the area inaccessible and might permit a ground level unmonitored release.

D. is incorrect, maintaining ventilation tripped would make the area inaccessible and might permit a ground level unmonitored release.

System No:

KA No: RO: SRO: 295038 EA1.06 3.5 3.6 System/Evolution:

High Off-Site Release Rate Category Statement:

Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE :

K/A Statement:

Plant ventilation Cog Level:

Memory TIER: GROUP: 1 1 10CFR: 41.7 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 4 Question No:

ILT-7064 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 5062.3C R 29a Explanation:

C - Div 3 DG starts at level 2 but will not close on to the bus if energized by the ERAT. The Div 2 DG starts on low voltage to the Div 2 Bus and will energize the bus. RCIC auto starts at -45" causing a main turbine and generator trip.

Distracters A, B, D not correct, only Div 3 DG starts at level 2 the other DGs start at level 1 (-145.5") or low bus voltage. If a bus is power by the RAT or ERAT the DG will not close in on the bus.

System No:

KA No: RO: SRO: 295005 AA2.08 3.2 3.3 System/Evolution:

Main Turbine Generator Trip Category Statement:

Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP :

K/A Statement:

Electrical distribution status Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 5 Question No:

ILT-7077 STA_Question RO Question SRO Question B Reference Provided:

Reference:

EOP-6 EOP-6 R 28 Explanation:

B is correct, pool level curve interpolation is not allowed therefore the 17 ft pool level curve must be used. This results in a maximum allowed RPV pressure of 750 psig.

A. is incorrect, see B C. is incorrect, see B D. is incorrect, see B Distracters are for the wrong suppression pool level. Interpolation is not allowed.

System No:

KA No: RO: SRO: 295007 AA2.01 4.1 4.1 System/Evolution:

High Reactor Pressure Category Statement:

Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE :

K/A Statement:

Reactor pressure Cog Level:

High TIER: GROUP: 1 2 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 6 Question No:

ILT-7080 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

None 4001.01, Reactor Coolant Leakage R 11 Explanation:

C. is correct, FPM channels trending up indicates a reactor coolant leak.

A. is incorrect, FW leak would not cause DW radiation increase.

B. is incorrect, IA leak would cause DW press to increase but not DW temp.

D. is incorrect, Temp and press going up and no change in FPM indicates a loss of VP.

System No:

KA No: RO: SRO: 295010 AA2.03 3.3 3.6 System/Evolution:

High Drywell Pressure Category Statement:

Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE :

K/A Statement:

Drywell radiation levels Cog Level:

High TIER: GROUP: 1 2 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 7 Question No:

ILT-2677 STA_Question RO Question SRO Question

d. Reference Provided:

Reference:

None 3203.01, CCW Explanation:

D. is correct, The RR pumps must be stopped within 1 minute of a loss of CCW.

A. is incorrect, The Condenser Vacuum pumps are normally cooled by TBCCW and CCW is back up cooling.

B. is incorrect, The Fuel Pool Cooling and Cleanup System can be cooled from SX.

C. is incorrect, The Service Air Compressors can only be cooled by CCW.

System No:

KA No: RO: SRO: 295018 AK2.01 3.3 3.4 System/Evolution:

Partial or Complete Loss of Component Cooling Water Category Statement:

Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:

K/A Statement:

System loads Cog Level:

Memory TIER: GROUP: 1 1 10CFR: CFR: 41.7 / 45.8

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 8 Question No:

ILT-7078 STA_Question RO Question SRO Question A. is correct Reference Provided:

Reference:

None 4200.01 Loss of AC power Explanation:

A. is correct. Over Crank on the Division one diesel generator is a valid LOCA trip.

B. is incorrect.138 KV line supplies the ERAT and it is lost C. is incorrect.138 KV line supplies the ERAT and it is lost Diesel Generator trips on Over Crank during a LOCA and is not available.

D. is incorrect. Diesel Generator trips on Over Crank during a LOCA and is not available.

System No:

KA No: RO: SRO: 203000 K1.08 3.5 3.5 System/Evolution:

RHR/LPCI: Injection Mode (Plant Specific)

Category Statement:

Knowledge of the physical connections and/or cause effect relationships between RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) and the following:

K/A Statement:

A.C. electrical power Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.2 to 41.9 /

45.7 to 45.8

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 9 Question No:

ILT-5256 STA_Question RO Question SRO Question D Reference Provided:

Reference:

NONE 4006.01, Loss of Shutdown Cooling R 4d Explanation:

D. is correct, both SDC suction isolation valves(1E12-F008/F009) close and "A" RHR pump trips when either valve leaves its full open seat.

A. in incorrect, both SDC suction isolation valves(1E12-F008/F009) close at level 3 (8.9")

B. is incorrect, both SDC suction isolation valves(1E12-F008/F009) close at level 3 (8.9")

C. is incorrect, both SDC suction isolation valves(1E12-F008/F009) close at level 3 (8.9")

System No:

KA No: RO: SRO: 295021 AA2.03 3.5 3.5 System/Evolution:

Loss of Shutdown Cooling Category Statement:

Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING :

K/A Statement:

Reactor water level Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 10 Question No:

ILT-7067 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 4979.07, Dropped or Struck Irradiated Fuel Bundle R 8e Explanation:

B. is correct, per the immediate actions of 4979.07.

A. is incorrect, this would be appropriate if the release had occurred in the containment C. is incorrect, the damaged bundle would be kept in the spent fuel pool. Spent fuel is not allowed to be stored long term in the containment D. is incorrect, radioactivity released in the Fuel building would by released out the Stack and not reach the containment.

System No:

KA No: RO: SRO: 295023 AK3.01 3.6 4.3 System/Evolution:

Refueling Accidents Category Statement:

Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS :

K/A Statement:

Refueling floor evacuation Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 11 Question No:

ILT-7068 STA_Question RO Question SRO Question D Reference Provided:

Reference:

None 5003-2A R 34C Explanation:

D. is correct, the RR HPUs should have shutdown and locked out the FCVs when the Drywell Pressure Annunciator came in. This has not occurred due to the associated annunciators not alarming.

A. is incorrect, the RR pumps do not need to be tripped unless drywell pressure continues to rise and reaches 1.68 psig and causes an isolation of CCW to the containment.

B. is incorrect, the mode switch should be placed in Shutdown if Drywell Pressure is 1.3 psig and rising.

C. is incorrect, the RR HPUs are st ill running and need to be locked out.

System No:

KA No: RO: SRO: 295024 2.4.50 4.2 4 System/Evolution:

High Drywell Pressure Category Statement:

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

K/A Statement:

Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.3 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 12 Question No:

ILT-7069 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 5067.06C R30c Explanation:

C. is correct, LLS is activated at 1103 psig and reduces the lowest relief function to 1033 psig to mitigate the effects of pressure loads on the containment from multiple SRV actuations.

A. is incorrect, the setpoint is 1033 psig.

B. is incorrect, the reason is pressure loads on the containment.

D. is incorrect, the setpoint is 1033 psig.

System No:

KA No: RO: SRO: 295025 EK3.01 4.2 4.3 System/Evolution:

High Reactor Pressure Category Statement:

Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE :

K/A Statement:

Safety/relief valve opening Cog Level:

Memory TIER: GROUP: 1 1 10CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 13 Question No:

ILT-7070 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None EOP-TB, Rev. 005 Explanation:

C. is correct, the blowdown is performed to prevent exceeding the Primary Containment Temperature Limit which is more limiting than the Primary Containment Pressure.

A. is incorrect, this blowdown will not prevent exceeding the Pressure Supp ression Pressure.

B. is incorrect, this blowdown will not prevent exceeding the Bo ron Injection Initiation Temperature.

D. is incorrect, this blowdown will not prevent exceeding the Net Positive Suction Head limits.

System No:

KA No: RO: SRO: 295026 EK3.01 3.8 4.1 System/Evolution:

Suppression Pool High Water Temperature Category Statement:

Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

K/A Statement:

Emergency/normal depressurization Cog Level:

Memory TIER: GROUP: 1 1 10CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 14 Question No:

ILT-7071 STA_Question RO Question SRO Question B Reference Provided:

Reference:

EOP-1 EOP-1 R 28 Explanation:

Correct Answer ANSWER: B With a Drywell Temperature of 310°F Narrow Range would be good to a level of 5 inches, and Upset Range would be good to 35 inches. A Containment Temperature of 280°F would allow Wide Range to be good to -136 inches. Since Upset Range level is below 35 inches it would not be valid.

a. Incorrect, Upset Range is not valid.

c. Incorrect, Upset Range is not valid and Narrow Range is valid.

d. Incorrect, Wide Range is valid.

System No:

KA No: RO: SRO: 295027 EK1.02 3 3.2 System/Evolution:

High Containment Temperature (Mark III Containment Only)

Category Statement:

Knowledge of the operational implications of the following concepts as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY):

K/A Statement:

Reactor water level measurement: Mark-III Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.8 to 41.10

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 15 Question No:

ILT-7072 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None Tech Spec LCO 3.6.5.5 Explanation:

B. is correct, the LCO limit is 150°F with an LDI limit of 146.53°F.

A. is incorrect, too low.

C. is incorrect, too high.

D. is incorrect, too high.

System No:

KA No: RO: SRO: 295028 2.2.38 3.6 4.5 System/Evolution:

High Drywell Temperature Category Statement:

Knowledge of conditions and limitations in the facility license.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 1 1 10CFR: 41.7 / 41.10 /

43.1 / 45.13

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 16 Question No:

ILT-7141 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None EOP Bases Explanation:

B is correct, the blowdown at 15 ft 1 in is based on inadequate horizontal vent coverage causing incomplete condensation during a LOCA.

A is incorrect, the ECCS suctions are near the bottom of the pool and are not threatened at 15 ft 1 in.

C is incorrect, all the curves above 15 ft 1 in on the Heat Capacity Limit are based on having enough capacity to absorb the heat from a blowdown but the 15 ft 1 in curve is based on horizontal vent coverage.

D is incorrect, this will occur however this is not the reason for blowing down. The incomplete condensation during a LOCA would add energy directly to the containment and threaten containment integrity from over pressurization. The blowdown eliminates this threat by reducing the amount of energy available during a LOCA.

System No:

KA No: RO: SRO: 295030 EK1.03 3.8 4.1 System/Evolution:

Low Suppression Pool Water Level Category Statement:

Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL:

K/A Statement:

Heat capacity Cog Level:

Memory TIER: GROUP: 1 1 10CFR: 41.8 to 41.10

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 17 Question No:

ILT-7073 STA_Question RO Question SRO Question D Reference Provided:

Reference:

None 4411.07, RPV Level Instrumentation R 5 Explanation:

D. Correct. None of the level instruments are in there operable ranges or conditions. Fuel Zone is pegged high and is good only if no recirculation pumps are running.

a. Incorrect, Fuel Zone would not be good because 'A' Recirc pump is still running.

b. Incorrect, other instruments are below usable levels and Fuel Zone is pegged high and cannot be used.

c. Incorrect, Shutdown, Upset, and Narrow range instruments are below their Usable Levels.

System No:

KA No: RO: SRO: 295031 EA2.01 4.6 4.6 System/Evolution:

Reactor Low Water Level Category Statement:

Ability to determine and/or interpret the followi ng as they apply to REACTOR LOW WATER LEVEL:

K/A Statement:

Reactor water level Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 18 Question No:

ILT-7062 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None CPS No. 4200.01, LOSS OF AC POWER Explanation:

C. is correct, DC load shedding must be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to ensure RCIC and SRVs remain available.

A. is incorrect, the Gland Seal Air Compressor is not needed to run RCIC and would be secured.

B. is incorrect, RCIC Lube Oil is cooled from the water being pumped by RCIC and will not be effected by the loss of power D. is incorrect, the Main Control Room can be cooled with a Gas Powered fan.

System No:

KA No: RO: SRO: 295003 AK1.02 3.1 3.4 System/Evolution:

Partial or Complete Loss of A.C. Power Category Statement:

Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :

K/A Statement:

Load shedding Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.8 to 41.10

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 19 Question No:

ILT-7063 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None USAR Chapter 8 Explanation:

B. is correct, The ampere-hour capacity of each battery is adequate to supply expected essential loads for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following station trip and loss of all a-c power coincident with a design-basis accident without battery terminal voltage falling below 84%.

A. is incorrect, The ampere-hour capacity of each battery is adequate to supply expected essential loads for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following station trip and loss of all a-c power coincident with a design-basis accident without battery terminal voltage falling below 84%

C. is incorrect, The ampere-hour capacity of each battery is adequate to supply expected essential loads for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following station trip and loss of all a-c power coincident with a design-basis accident without battery terminal voltage falling below 84%

D. is incorrect, The ampere-hour capacity of each battery is adequate to supply expected essential loads for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following station trip and loss of all a-c power coincident with a design-basis accident without battery terminal voltage falling below 84%

System No:

KA No: RO: SRO: 295004 AA2.03 2.8 2.9 System/Evolution:

Partial or Complete Loss of D.C. Power Category Statement:

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

K/A Statement:

Battery voltage Cog Level:

Memory TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 20 Question No:

ILT-7076 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None DARs Trend Explanation:

C. is correct, the VAR loading lowers due to a loss of a major load on the grid therefore the generator output voltage had to be lowered by the operator. This causes the plant bus voltages to lower and thus motors must draw more current to maintain the same power.

A. is incorrect excitation remains constant B. is incorrect excitation remains constant D. is incorrect VAR loading lowers System No:

KA No: RO: SRO: 700000 AK201 3.1 3.2 System/Evolution:

Generator Voltage and Electric Grid Disturbances Category Statement:

Knowledge of the interrelations between GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following:

K/A Statement:

Motors Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.4, 41.5, 41.7, 41.10 /

45.8 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 21 Question No:

ILT-5362 STA_Question RO Question SRO Question D. Reference Provided:

Reference:

None 4004.02, Loss of Vacuum R 2a Explanation:

D. Correct - Reactor Recirculation System Runback Signal due to trip of both TDRFP's which will result in a level 4.

A. Incorrect - TBV's are already shut and close last on lowering vacuum.

B. Incorrect - MSIV closure will not occur first.

C. Incorrect - Main Turbine trip scram not enabled yet.

System No:

KA No: RO: SRO: 295002 AA1.08 2.6 2.7 System/Evolution:

Loss of Main Condenser Vacuum Category Statement:

Ability to operate and/or monitor the following as they apply to LOSS OF MAIN CONDENSER VACUUM :

K/A Statement:

Recirculating flow control system Cog Level:

High TIER: GROUP: 1 2 10CFR: 41.7 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 22 Question No:

ILT-7065 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 4100.01, Reactor Scram R 19c Explanation:

C is correct, Per CPS 4100.01, Section 4.2 NOTE. Operators should lower reactor pressure to about 600 psig to minimize the RPV-to-FW delta-T that exists during a plant cooldown.

A, B and D are incorrect pressures.

System No:

KA No: RO: SRO: 295006 2.1.20 4.6 4.6 System/Evolution:

SCRAM Category Statement:

Ability to interpret and execute procedure steps.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.12 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 23 Question No:

ILT-6486 STA_Question RO Question SRO Question A Reference Provided:

Reference:

CPS No. 4003.01F003 RSP - SATURATED CPS No. 4003.01F003 RSP - SATURATED TEMPERATURE/PRESSURE CORRELATION or Steam Tables and calculator.

Explanation:

Answer: A Explanation: The cooldown rate is excessive (135ºF/hr) and will exceed 100ºF/hr if the rate of depressurization is not reduced. Since the RCIC system is controlling reactor pressure it's flowrate should be reduced in an attempt to control cooldown rate.

Distracters:

B is incorrect because increasing RCIC flow would further aggravate the already high cooldown rate.

C is incorrect because maintaining this flow rate would exceed the cooldown rate limit.

D is incorrect because shifting suctions will not prevent exceed the cooldown rate limit and there is no driving reason to shift RCIC suctions.

System No:

KA No: RO: SRO: 295016 AA1.08 4 4 System/Evolution:

Control Room Abandonment Category Statement:

Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT:

K/A Statement:

Reactor pressure Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.7 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 24 Question No:

ILT-7079 STA_Question RO Question SRO Question A Reference Provided:

Reference:

EOP-6 R 28 EOP-6 R 28 Explanation:

A is correct, one loop of RHR can be diverted to Containment Spray B is incorrect, one loop of LPCI is needed for Core Cooling and should not be diverted to Containment Spray C is incorrect, temperature is the issue not pressure.

D is incorrect, Shutdown Service Water could be lined up to spray the Containment but flow would be too low to be effective. The SX connection to RHR is with a 4" line.

System No:

KA No: RO: SRO: 295011 2.4.6 3.7 4.7 System/Evolution:

High Containment Temperature (Mark III Containment Only)

Category Statement:

Knowledge of EOP mitigation strategies K/A Statement:

Cog Level:

High TIER: GROUP: 1 2 10CFR: 41.10 /43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 25 Question No:

ILT-5993 STA_Question RO Question SRO Question A The control rod pattern does not match the pattern restraints of the Rod Pattern Controller at high powers. The Rod Pattern Controller uses Turbine First Stage Pressure to determine power with the Rod Pattern Controller bypassed above 16.7%. Reference Provided:

Reference:

None 4410.00C012, Defeating ATWS Interlocks R 4 Explanation:

A is correct, the control rod pattern does not match the pattern restraints of the Rod Pattern Controller at high powers. The Rod Pattern Controller uses Turbine First Stage Pressure to determine power with the Rod Pattern Controller bypassed above 16.7%.

B is incorrect, The Turbine First Stage Pressure trip setpoint is set at minimum.

C is incorrect, ATWS rod positions may not match rod pattern in RCIS.

D is incorrect, ATWS rod positions may not match rod pattern in RCIS.

System No:

KA No: RO: SRO: 295015 AK3.01 3.4 3.7 System/Evolution:

Incomplete SCRAM Category Statement:

Knowledge of the reasons for the following responses as they apply to INCOMPLETE SCRAM :

K/A Statement:

Bypassing rod insertion blocks Cog Level:

Memory TIER: GROUP: 1 2 10CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 26 Question No:

ILT-7066 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 3007.01, Preparation and Recovery From Refueling Explanation:

C. is correct, a backup pneumatic supply is installed for the gate seals during the preparation for refueling as a corrective action for a pool draindown event caused by a loss of IA.

A. is incorrect, the only thing that will stop upward movement of the Main Hook is High Radiation.

B. is incorrect, the backup pneumatic supply will prevent this.

D. is incorrect, the FC filter demins will isolate but the bypass will open and prevent the pumps from tripping.

System No:

KA No: RO: SRO: 295019 K2.10 2.8 2.8 System/Evolution:

Partial or Complete Loss of Instrument Air Category Statement:

Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following:

K/A Statement:

Fuel pool cooling Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.7 / 45.8

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 27 Question No:

ILT-1456 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

None 4001.02 C001 Automatic isolation checklist. Rev. 14E Explanation:

C. Correct. F009 will not close due to not having power but the F008 will shut and shutdown cooling will be lost and reactor coolant circulation will need to be verified by an alternate method.

A. Incorrect. Isolation signal is valid F009 valve does not have power since it is an MOV it fails as is.

B. Incorrect. Isolation signal is valid F009 valve does not have power since it is an MOV it fails as is.

D. Incorrect. Isolation signal is valid on high pressure the group three isolation will occur.

System No:

KA No: RO: SRO: 205000 A2.03 3.2 3.2 System/Evolution:

Shutdown Cooling System (RHR Shutdown Cooling Mode)

Category Statement:

Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

A.C. failure Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.5/45.6 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 28 Question No:

ILT-7081 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 3302.01, Reactor Recirculation R 30 Explanation:

C is correct, Securing CRD injection to a RR pump which has been secured and isolated due to a seal leak will cause an increase in drywell airborne activity as the loop depressurizes to atmosphere through the seal.

A is incorrect, Drywell floor drain flow will either increase or remain the same due to further degradation of the seal.

B is incorrect, seal temperatures will increase due to flow of hot water past the seals.

D is incorrect, loss of CRD injection will not effect the upper wear ring.

System No:

KA No: RO: SRO: 295022 AK2.01 2.8 3 System/Evolution:

Loss of CRD Pumps Category Statement:

Knowledge of the interrelations between LOSS OF CRD PUMPS and the following:

K/A Statement:

Recirculation system: Plant-Specific Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.7 / 45.8

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 29 Question No:

ILT-6345 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

None EOP-8 Secondary Containment Control Bases R 5 Explanation:

C. Correct - Fuel Bldg Ventilation trips on a high rad condition of 10 mr/hr. SGTS starts to maintain Secondary Containment Integrity but does not provide the same capacity as the Fuel Bldg Ventilation, so area temperatures could rise. A. Incorrect - containment integrity is not jeopardized solely by FB radiation level.

B. Incorrect - Secondary Containment integrity will not be affected solely by FB radiation level.

D. Incorrect - since VG starts, ground level release may actually lower.

System No:

KA No: RO: SRO: 295034 EK1.02 4.1 4.4 System/Evolution:

Secondary Containment Ventilation High Radiation Category Statement:

Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION:

K/A Statement:

Radiation releases Cog Level:

High TIER: GROUP: 1 2 10CFR: 41.8 to 41.10

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 30 Question No:

ILT-1309 STA_Question RO Question SRO Question D Reference Provided:

Reference:

None M05-1078 Sheet 2 Rev J Explanation:

D is correct, with the flow controller in manual the flow control valve will not respond to a high flow and total system flow can exceed pump runout flow.

A is incorrect, with the flow controller in manual the flow control valve will not respond to a high flow B is incorrect, with the flow controller in manual the flow control valve will not respond to a high flow C is incorrect, with the flow controller in manual the flow control valve will not respond to a high flow and this will result in more cooling water flow than there should be for the conditions.

System No:

KA No: RO: SRO: 201001 A1.03 2.9 2.8 System/Evolution:

Control Rod Drive Hydraulic System Category Statement:

Ability to predict and/or monitor changes in parameters associated with operating the CONTROL ROD DRIVE HYDRAULIC SYSTEM controls including:

K/A Statement:

CRD system flow Cog Level:

High TIER: GROUP: 2 2 10CFR: 41.5 / 45.5

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 31 Question No:

ILT-4822 STA_Question RO Question SRO Question A. Reference Provided:

Reference:

NONE 3313.01E001 Low Pressure Core Spray Electrical Line Up Explanation:

A. Correct - powered AB MCC 1A3.

B. Incorrect - powered DC MCC 1A.

C. Incorrect - powered 1E22-S002.

D. Incorrect - powered AB MCC 1B2.

System No:

KA No: RO: SRO: 209001 K2.02 2.5 2.7 System/Evolution:

Low Pressure Core Spray System Category Statement:

Knowledge of electrical power supplies to the following:

K/A Statement:

Valve power Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 32 Question No:

ILT-7082 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None CPS No. 4100.01, Reactor Scram R 19c Explanation:

A is correct, Per CPS 3304.02, Step 8.2.11 B is incorrect, Used to display either one or both channels of the display (not available at this time).

C is incorrect, Cannot be determined until scram is reset.

D is incorrect, Can be determined using ID generator.

System No:

KA No: RO: SRO: 201005 A4.03 3.4 3.3 System/Evolution:

Rod Control and Information System (RCIS)

Category Statement:

Ability to manually operate and/or monitor in the control room:

K/A Statement:

Back panel indicating lights: BWR-6 Cog Level:

High TIER: GROUP: 2 2 10CFR: 41.7 / 45.5 to 45.8 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 33 Question No:

ILT-7083 STA_Question RO Question SRO Question D Reference Provided:

Reference:

None 9041.01, Jet Pump Operability R 34b Explanation:

D is correct - "A" loop flow will remain unchanged, "B" loop flow will remain unchanged and core flow will decrease 5 percent. A is incorrect - Each recirculation pump suction line elbow is a specially designed flow element. Instrument taps on the flow elements provide input to differential pressure transmitters, which, in turn provide recirculation loop flow information there for "A" and "B" loop flow will remain unchanged. Core flow is the summation of all (20) Jet pump flows, so core flow will decrease by only 5 percent.

B is incorrect - Each recirculation pump suction line elbow is a specially designed flow element. Instrument taps on the flow elements provide input to differential pressure transmitters, which, in turn provide recirculation loop flow information there for "A" and "B" loop flow will remain unchanged. Core flow is the summation of all (20) Jet pump flows, so core flow will decrease by only 5 percent.

C is incorrect - Each recirculation pump suction line elbow is a specially designed flow element. Instrument taps on the flow elements provide input to differential pressure transmitters, which, in turn provide recirculation loop flow information there for "A" and "B" loop flow will remain unchanged. Core flow is the summation of all (20) Jet pump flows, so core flow will decrease by only 5 percent.

System No:

KA No: RO: SRO: 216000 G2.1.45 4.3 4.3 System/Evolution:

Nuclear Boiler Instrumentation Category Statement:

Ability to identify and interpret diverse indications to validate the response of another indication.

K/A Statement:

Cog Level:

High TIER: GROUP: 2 2 10CFR: 41.7 / 43.5 / 45.4

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 34 Question No:

ILT-7084 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None 3312.01, RHR R 38a Explanation:

A is correct, the equalizing valve opening will cause the flow transmitters to see a low D/P and low flow. The Pump minimum flow valve opens with flow less than 1100 gpm. This will direct some flow back to the suppression pool bypassing the heat exchanger while total system flow remains the same due to a restricting orifice.

B is incorrect, total flow will remain the same.

C is incorrect, total flow will remain the same.

D is incorrect, flow through the min fl ow valve will bypass the heat exchanger.

System No:

KA No: RO: SRO: 219000 K4.05 3 3.2 System/Evolution:

RHR/LPCI: Torus/Suppression Pool Cooling Mode Category Statement:

Knowledge of RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE design feature(s) and/or interlocks which provide for the following:

K/A Statement:

Pump minimum flow protection Cog Level:

High TIER: GROUP: 2 2 10CFR: 41.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 35 Question No:

ILT-7085 STA_Question RO Question SRO Question

d. Reference Provided:

Reference:

None 3408.01, VR/VQ R 16f Explanation:

D. Correct - There are two Pressure Control Modulating Dampers, damper 1VR03Y on the CBV supply piping, and damper 1VR04Y on the CCP supply piping. Note that for CCP, 1VR04Y is actually inside Containment, downstream of the Secondary Cooling Coil.

A. Incorrect - VR must be isolated during power operation.

B. Incorrect - VR must be isolated during power operation.

C. Incorrect - Supply air to containment.

System No:

KA No: RO: SRO: 223001 K5.08 2.7 2.8 System/Evolution:

Primary Containment System and Auxiliaries Category Statement:

Knowledge of the operational implications of the following concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES :

K/A Statement:

Pressure measurement Cog Level:

Memory TIER: GROUP: 2 2 10CFR: 41.5 / 45.3

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 36 Question No:

ILT-7086 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 3302.01E001, Reactor Recirculation Electrical Lineup R Explanation:

C is correct, the fast speed power supply to the 1A Recirc Pump is 6.9 KV bus 1A A is incorrect, the power supply to the MDRFP is 6.9 KV bus 1B.

B is incorrect, the power supply to the #1 Service Air Compressor is 4.16 KV bus 1B.

D is incorrect, the power supply to the "A" Drywell Chiller is 4.16 KV bus 1A1.

6.9KV loads 1A 1B CW A CW B CW C MDRFP RR A RR B System No:

KA No: RO: SRO: 202001 K2.01 3.2 3.2 System/Evolution:

Recirculation System Category Statement:

Knowledge of electrical power supplies to the following:

K/A Statement:

Recirculation pumps: Plant-Specific Cog Level:

Memory TIER: GROUP: 2 2 10CFR: 41.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 37 Question No:

ILT-7087 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 3800.02, Area Operator Logs R 18f Explanation:

C is correct, the SSE can be fed directly from Main Steam which taps into the same line as the extraction steam. A failure of the Non-return valves would allow main steam to be backfeed through the extraction line to the Main Turbine and would cause an overspeed.

A is incorrect, the SSE produces ~80 ps ig steam which is lower than the High Pressure Feedwater Heaters.

B is incorrect, the MOV stroke times are too long to prevent a turbine overspeed.

D is incorrect, the drain lines are provided to remove moisture from the extraction steam lines during startup.

System No:

KA No: RO: SRO: 239001 K1.10 2.7 2.8 System/Evolution:

Main and Reheat Steam System Category Statement:

Knowledge of the physical connections and/or cause effect relationships between MAIN AND REHEAT STEAM SYSTEM and the following:

K/A Statement:

Extraction steam system Cog Level:

Memory TIER: GROUP: 2 2 10CFR: 41.2 to 41.9 /

45.7 to 45.8

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 38 Question No:

ILT-7089 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 5002.04 4F R 33a Explanation:

B is correct, only the low suction pressure will alarm and the operator then needs to start an additional Condensate pump. A is incorrect, starting an additional Condensate pump will restore suction pressure and a reactor scram is not required.

C is incorrect, The B TDRFP low suction pressure trip has a 6 second time delay. the A TDRFP low suction pressure trip has a 12 second time delay. The B would trip first restoring suction pressure to prevent the A from tripping.

D is incorrect, for the MDRFP to Auto start both TDRFPs must trip System No:

KA No: RO: SRO: 256000 A2.03 2.8 2.9 System/Evolution:

Reactor Condensate System Category Statement:

Ability to (a) predict the impacts of the following on the REACTOR CONDENSATE SYST EM; and (b) ba sed on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

Valve openings Cog Level:

High TIER: GROUP: 2 2 10CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 39 Question No:

ILT-0658 STA_Question RO Question SRO Question

a. Reference Provided:

Reference:

None 5002.01 1Q R 31e Explanation:

A. Correct - The Level 8 TDRFP trip is a 2 out of 3 logic. With A and C channels failed high, the trip logic is complete. The TDRFPs trip.

B. Incorrect - MDRFP has 2 of 3 logic also and will not start.

C. Incorrect - B channel is selected for the input to FWLC. The transmitters are also used for the High RPV level trip logic and are 2 out of 3 so the TDRFPs trip.

D. Incorrect - See "a.". There is no shift to MANUAL on the flow controllers.

System No:

KA No: RO: SRO: 259001 K6.07 3.8 3.8 System/Evolution:

Reactor Feedwater System Category Statement:

Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR FEEDWATER SYSTEM:

K/A Statement:

Reactor water level control system.

Cog Level:

High TIER: GROUP: 2 2 10CFR: 41.7 / 45.7

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 40 Question No:

ILT-7102 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 5050.07 7M R 32b Explanation:

B Correct - Per CPS 5140.64, pages 2 and 3. The 'ladder logic' for this system is: A or D, with B or C. Of the several

'failure' types presented in these 4 choices, the only one that does not input to the isolation logic is the 'Comm Fail' type.

The High Rad signal shifts VC to the High Rad mode which places the Supply and Makeup Air Filter Package in service.

A Incorrect - will shift to the High Rad mode.

C Incorrect - will shift to the High Rad mode.

D Incorrect - will shift to the High Rad mode.

System No:

KA No: RO: SRO: 272000 K3.10 2.9 3.3 System/Evolution:

Radiation Monitoring System Category Statement:

Knowledge of the effect that a loss or malfunction of the RADIATION MONITORING System will have on following:

K/A Statement:

Control room ventilation: Plant-Specific Cog Level:

Memory TIER: GROUP: 2 2 10CFR: 41.5 / 45.3

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 41 Question No:

ILT-7090 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 3213.01 Fire Detection and Protection R 25d Explanation:

B is correct, with no system leakage the Jockey pump w ill run ~45 seconds every 2-3 hours to maintain system pressure. A is incorrect, if system leakage is higher than normal the jockey pump is placed in "Hand" and run continuous to maintain system pressure.

C is incorrect, the horizontal fire pump backs up the Diesel fire pumps as a source of system flow D is incorrect, the Diesel fire pumps only run when system flow is required.

System No:

KA No: RO: SRO: 286000 A1.01 2.9 2.9 System/Evolution:

Fire Protection System Category Statement:

Ability to predict and/or monitor changes in parameters associated with operating the FIRE PROTECTION SYSTEM controls including:

K/A Statement:

System pressure Cog Level:

Memory TIER: GROUP: 2 2 10CFR: 41.5 / 45.5

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 42 Question No:

ILT-7091 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 3402.01, Control Room HVAC R 25c Explanation:

B is correct, Smoke opens the filter inlet and outlet and closes the bypass A is incorrect, the filter is isolated C is incorrect, the bypass is open D is incorrect, the deluge valves are open to extinguish a fire in the filter System No:

KA No: RO: SRO: 290003 A3.01 3.3 3.5 System/Evolution:

Control Room HVAC Category Statement:

Ability to monitor automatic operations of the CONTROL ROOM HVAC including:

K/A Statement:

Initiation/reconfiguration Cog Level:

High TIER: GROUP: 2 2 10CFR: 41.7 / 45.7

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 43 Question No:

ILT-7092 STA_Question RO Question SRO Question A. Reference Provided:

Referece: n None EOP-1 Explanation:

A. Correct. Use the condensate and condensate booster systems to inject to recover level preferred injection system.

B. Incorrect. Steam cooling is only used during an ATWS.

C. Incorrect. Core cooling is assured through submergence emergency depressurization with out attempting to use condensate and booster systems is not allowed.

D. Incorrect. ADS should not be inhibited until the ADS timer starts which is level one (-145.5").

System No:

KA No: RO: SRO: 209002 K3.03 3.9 4.1 System/Evolution:

High Pressure Core Spray System Category Statement:

Knowledge of the effect that a loss or malfunction of the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) will have on following:

K/A Statement:

Adequate core cooling: BWR-5,6 Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.7, 45.4

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 44 Question No:

ILT-7101 STA_Question RO Question SRO Question A. Reference Provided:

Reference:

Figures of SC A and B indications CPS 3314.01, Rev. 11b, Standby Liquid Control (SC)

Explanation:

A. is correct, Both SLC pumps are running. Squib valve B is open (indicated by squib B continuity light OFF) and squib valve A is closed (continuity light is ON). Therefore, flow from the both SLC pump are through squib valve B into the reactor vessel.

B is incorrect, Both of the SLC pump is running.

C is incorrect, The squib valve A continuity light is ON, the squib has NOT fired and the valve is NOT open.

D is incorrect, The SLC pumps are running.

System No:

KA No: RO: SRO: 211000 K4.04 3.8 3.8 System/Evolution:

Standby Liquid Control System Category Statement:

Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

K/A Statement:

Indication of fault in explosive valve firing circuits Cog Level:

High TIER: GROUP: 2 1 10CFR: 55.41(b)(7)

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 45 Question No:

ILT-7093 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None OP-AA-300, Reactivity Management R 4 Explanation:

A is correct. Per Section 4.2.11.1.B of OP-AB-300-1003, the Reactor Engineer must be present in the MCR at this time. Per OP-AA-300, Section 4.5, although it is 'acceptable to utilize another SRO to perform the reactivity management function' it is not required. The on-shift CRS may act to perform this function.

B is incorrect, see A C is incorrect, see A D is incorrect, see A System No:

KA No: RO: SRO: Generic 2.1.01 3.8 4.2 System/Evolution:

Category Statement:

Knowledge of conduct of operations requirements.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: 41.10 / 45.13

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 46 Question No:

ILT-7094 STA_Question RO Question SRO Question D Reference Provided:

Reference:

None OP-AA-103-105, Limitorque Motor-Operated Valve Explanation:

D is correct; Passport contains locations of plant equipment and the valve must be manually unseated after it has been manually seated.

A is incorrect, system procedure valve lineups do not include motor operated valve's physical location and it must be manually unseated.

B is incorrect, the valve must be manually unseated C is incorrect, system procedure valve lineups do not include motor operated valve's physical locations System No:

KA No: RO: SRO: Generic 2.1.30 4.4 4 System/Evolution:

Category Statement:

Ability to locate and operate components, including local controls.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: 41.7 / 45.7

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 47 Question No:

ILT-7095 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None CPS Operational Requirements Manual Bases 5.3.1 R 64 Explanation:

B is correct, the higher Coolant temperatures and de-airation of the Condensate in Mode 1 reduce oxygen concentration and the effect of chloride is not as great with low oxygen. Therefore the upper limit on Chloride is allowed to be higher in Mode 1. A is incorrect, oxygen is lower.

C is incorrect, the Chloride limit is higher.

D is incorrect, oxygen is lower and the Chloride limit is higher.

System No:

KA No: RO: SRO: Generic 2.1.34 2.7 3.5 System/Evolution:

Category Statement:

Knowledge of primary and secondary plant chemistry limits.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: 41.10 / 43.5 /

45.12 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 48 Question No:

ILT-0201 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None CPS Tech Specs Definitions Explanation:

B. Correct - Capable of performing its specified safety function with its support systems capable of performing their required support functions.

A. Incorrect - This is the definition of a Safety Limit.

C. Incorrect - It is required to have all of its support systems capable of performing their required support functions.

D. Incorrect - This is t he definition of a Surveillance.

System No:

KA No: RO: SRO: Generic 2.2.38 3.6 4.5 System/Evolution:

Category Statement:

Knowledge of conditions and limitations in the facility license.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: 41.7 / 41.10 /

43.1 / 45.13

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 49 Question No:

ILT-6698 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 1406.01 ANNUNCIATOR TRACKING PROGRAM R 14c Explanation:

B - Correct - IAW CPS 1406.01 ANNUNCIATOR TRACKING PROGRAM, an orange flag is used on a Partially disabled annunciator.

A - Incorrect - Blue is out of service.

C - Incorrect - Red is a fully disabled annunciator.

D - Incorrect - Any color except red, blue and orange is allowed to be used for this.

System No:

KA No: RO: SRO: Generic 2.2.43 3 3.3 System/Evolution:

Category Statement:

Knowledge of the process used to track inoperable alarms.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 50 Question No:

ILT-7096 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

None 3305.01 Reactor protective system Revision 11 B Explanation:

C. Correct these indications are available on P-680, using sensor bypass will clear the upscale alarms on P-680.

A. Incorrect. APRM upscales do NOT cause a half scram our logic is two of four for sensor logic and there is no half scram B. Incorrect. APRM upscales do NOT cause a half scram our logic is two of four for sensor logic and there is no half scram. D. Incorrect. Bypassing LPRMS will not clear the alarms.

System No:

KA No: RO: SRO: 215005 K4.01 3.7 3.7 System/Evolution:

Average Power Range Monitor/Local Power Range Monitor System Category Statement:

Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following:

K/A Statement:

Rod withdrawal blocks Cog Level:

High TIER: GROUP: 2 1 10CFR: CFR: 41.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 51 Question No:

ILT-1404 STA_Question RO Question SRO Question

d. Reference Provided:

Reference:

None 3306.01, SRM/IRM Explanation:

D. Correct - 100 on range 10 = 40% Reactor power.

A. Incorrect - this would be for 100 on range 4.

B. Incorrect - this would be for 100 on range 6.

C. Incorrect - this would be for 100 on range 8.

System No:

KA No: RO: SRO: 215003 K5.01 2.6 2.7 System/Evolution:

Intermediate Range Monitor (IRM) System Category Statement:

Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :

K/A Statement:

Detector operation Cog Level:

Memory TIER: GROUP: 2 1 10CFR: CFR: 41.5 / 45.3

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 52 Question No:

ILT-5314 STA_Question RO Question SRO Question B. High voltage power supplies Reference Provided:

Reference:

None CPS 3306.01 E001 SRM-IRM ELECTRICAL LINEUP Explanation:

B. Correct.

A. Incorrect, powered from CB MCC 1C C. Incorrect, powered from AB MCC 1F D. Incorrect, powered from CB MCC D System No:

KA No: RO: SRO: 215004 K2.01 2.6 2.8 System/Evolution:

Source Range Monitor (SRM) System Category Statement:

Knowledge of electrical power supplies to the following:

K/A Statement:

SRM channels/detectors Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 53 Question No:

ILT-7142 STA_Question RO Question SRO Question B. Reference Provided:

Reference:

None CPS 4100.01 Explanation:

B. is correct, a scram is required the scram setpoint in S/U is 15%.

A. is incorrect, lowering recirc flow control valve position in slow speed has little effect and a scram is required.

C. is incorrect, inserting control rods will clear the rod block however a scram is required.

D. is incorrect, this will clear a rod block however is NOT allowed reactor power is too high and a scram is required.

System No:

KA No: RO: SRO: 212000 A2.06 4.1 4.2 System/Evolution:

Reactor Protection System Category Statement:

Ability to (a) predict the impacts of the following on he REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

High reactor power Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.5/45.6 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 54 Question No:

ILT-6859 STA_Question RO Question SRO Question B Reference Provided:

Reference:

NONE CPS 4009.01 Inadvertent opening safety relief valve Explanation:

B is correct, 4009.01 lists the tailpipe temperature of on open SRV as > 375°F A is incorrect, 5066-5B, ADS ORSAFETY RELIEFVALVE LEAKING ADS, HEAD VENT, or SRV leaking (typically 230°F to 270°F) C is incorrect, 420°F is too high.

D is incorrect, 450°F is normal operating temperature.

System No:

KA No: RO: SRO: 218000 A3.02 3.6 3.7 System/Evolution:

Automatic Depressurization System Category Statement:

Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:

K/A Statement:

ADS valve tail pipe temperatures Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.7/45.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 55 Question No:

ILT-7103 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None CPS 5063-2E, Rev. 31a, RCIC Storage Tank Level Low Explanation:

B is correct, RCIC suction transfers from RCIC Storage Tank to the RCIC Storage Tank low level.

RCIC is normally aligned to take suction on the Storage Tank through the 1E51-F010 valve and will automatically transfer suction to the Suppression Pool through the 1E51-F031 valve on high Suppression Pool level, 19' 11.5", or low Storage Tank level, 3' 2.25".

A is incorrect - The suction transfer is designed to prevent a loss of suction which could cause an overspeed trip.

C is incorrect - HPCS injection valve automatically cycles to maintain RPV water level between L-2 and L-8.

D is incorrect - HPCS minflow will already be open.

System No:

KA No: RO: SRO: 217000 A3.01 3.5 3.5 System/Evolution:

Reactor Core Isolation Cooling System (RCIC)

Category Statement:

Ability to monitor automatic operations of the REAC TOR CORE ISOLATION COOLING SYSTEM (RCIC) including:

K/A Statement:

Valve operations Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.7/45.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 56 Question No:

ILT-7105 STA_Question RO Question SRO Question A. Reference Provided:

Reference:

None. 3306.01 Source-intermediate range monitors (SRM-IRM)

Explanation:

A. Correct, with the shorting links removed and an upscale alarm will cause a full reactor scram and a Rod Block.

B. Incorrect, the upscale will also cause a rod block.

C. Incorrect, with the shorting links removed any neutron monitoring upscale will cause a full scram.

D. Incorrect, with the shorting links removed any neutron monitoring upscale will cause a full scram.

System No:

KA No: RO: SRO: 215004 K6.04 2.9 2.9 System/Evolution:

Source Range Monitor (SRM) System Category Statement:

Knowledge of the effect that a loss or malfunction of the following will have on the SOURCE RANGE MONITOR (SRH)

SYSTEM : K/A Statement:

Detectors Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.7/45.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 57 Question No:

ILT-1000 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None *This question was on the 06-01NRC exam*

CPS 5005.01 1J APRM D UPSC Trip or INOP R 29b Explanation:

A is correct, channel A is tripped when de-energized. Channel "D" was tripped by the LPRM Count Circuit when LPRMs total went below 16, with 18 bypassed.

B is incorrect, the reactor automatically scrams immediately but if it did not scram a Rod Block would be initiated.

C is incorrect, the reactor automatically scrams immediately due to the inop APRMs.

D is incorrect, the reactor automatically scrams immediately due to the inop APRMs.

System No:

KA No: RO: SRO: 212000 K6.05 3.5 3.8 System/Evolution:

Reactor Protection System Category Statement:

Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR PROTECTION SYSTEM:

K/A Statement:

RPS sensor inputs Cog Level:

High TIER: GROUP: 2 1 10CFR: CFR: 41.7 / 45.7

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 58 Question No:

ILT-7106 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None HU-AA-101, Rev. 3, Human Performance Tools and Explanation:

A is correct, a Danger tag to be hung on the 1G33-F043A, RT Pump A suction isolation valve, handwheel.

The Shift Manager may waive verification requirements for ALARA concerns.

b, c, and d are incorrect - The components in these choices are in areas where radiation levels are not a factor. The candidate must understand that these components are in very low, or no, radiation areas and independent verification would not be waived.

System No:

KA No: RO: SRO: Generic 2.3.12 3.2 3.7 System/Evolution:

Generic Category Statement:

Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

K/A Statement:

Cog Level:

High TIER: GROUP: 3 10CFR: 41.12 / 45.9 /

45.10 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 59 Question No:

ILT-4847 STA_Question RO Question SRO Question D. Reference Provided:

Reference:

None 3312.03, RHR R 6 Explanation:

D. Correct - RHR A requires local valve operation which will result in radiation exposure to operators. RHR B uses two MOVs to control rejection.

A. Incorrect - B is preferred B. Incorrect - B is preferred C. Incorrect - Plugged tubes are not a factor System No:

KA No: RO: SRO: GENERIC 2.3.14 3.4 3.8 System/Evolution:

Radiation Control Category Statement:

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: CFR: 41.12 /

43.4 / 45.10

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 60 Question No:

ILT-7135 STA_Question RO Question SRO Question B Reference Provided:

Reference:

NONE 4001.02C001 R 14e Explanation:

B. Correct - Per CPS 4001.02C001, page 8, this is a Group 8 valve. Div 1 NSPS services the Load Driver for the Inboard valves. A ZERO input to the Load Driver produces an energized function to close the Inboard valves.

A. Incorrect - This is a Group 5 valve.

C. Incorrect - This is a Group 4 valve.

D. Incorrect - This is a Group 9 valve.

System No:

KA No: RO: SRO: 223002 K6.01 3.1 3.3 System/Evolution:

Primary Containment Isolation System/Nuclear Steam Supply Shut-Off Category Statement:

Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF :

K/A Statement:

A.C. electrical distribution Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.7/45.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 61 Question No:

ILT-7148 STA_Question RO Question SRO Question A. Reference Provided:

Reference:

None 4005.01 Loss of feedwater heating. Revision 017 Explanation:

A. Correct. Reactor power rises and stays higher due to loss of feedwater heating B. Incorrect. Reactor water level swells and is then returned to its setpoint by Feedwater level control.

C. Incorrect. Reactor water level swells not lowers and is returned to its setpoint by Feedwater level control.

D. Incorrect. MW electrical lowers and will remain less than it was due to steam bypassing the turbine.

System No:

KA No: RO: SRO: 239002 A1.06 3.7 3.8 System/Evolution:

Relief/Safety Valves Category Statement:

Ability to predict and/or monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including:

K/A Statement:

Reactor power Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.7/45.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 62 Question No:

ILT-7109 STA_Question RO Question SRO Question C. CPS No. 5002.03, Page 1 calls for reducing turbine speed until alarm clears. Performed this way to allow "B" RFP to remain on the Master Controller.

Reference Provided:

Reference:

NONE CPS No. 5002.03, Page 1 calls for reducing turbine Explanation:

C. Correct. CPS No. 5002.03, Page 1 calls for reducing turbine speed until alarm clears. Performed this way to allow "B" RFP to remain on the Master Controller.

A. Incorrect. This is not required one TRFP can support 65% Rx power.

B. Incorrect. This will hinder the actions and cause more load on the TDRFP not less.

D. Incorrect. This will due nothing to the FWLC system unless the start up level controller is active and this turbine is to be slowed down.

System No:

KA No: RO: SRO: 259002 K5.01 3.1 3.1 System/Evolution:

Reactor Water Level Control System Category Statement:

Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM:

K/A Statement:

GEMAC/Foxboro/Bailey controller operation: Plant-Specific Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.5/43.5 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 63 Question No:

ILT-4874 STA_Question RO Question SRO Question A. Reference Provided:

Reference:

NONE 3319.01 Standby Gas Treatment (VG) Revision 16 Explanation:

A Correct. 1VF09Y shuts as Fuel Building Vents ISOLATE, the AXM 0RIX-PR008 is RUNNING.

B Incorrect. AXM 0RIX-PR008 is RUNNING.

C Incorrect. 1VF09Y shuts.

D Incorrect. 1VF09Y shuts, AXM 0RIX-PR008 is RUNNING..

System No:

KA No: RO: SRO: 261000 A4.01 3.2 4 System/Evolution:

Standby Gas Treatment System Category Statement:

Ability to manually operate and/or monitor in the control room:

K/A Statement:

Off-site release levels: Plant-Specific Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.7/45.5 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 64 Question No:

ILT-3420 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

NONE 3501.10 High Voltage auxiliary power system Revision 26 Explanation:

C. Correct. Loads auto transfer to the ERAT, load shed does not occur, EDGs do not start unless ERAT does not pick up the bus. A. Incorrect. no load shed occurs only on LOCA signal, EDGs do not start.

B Incorrect. no load shed occurs only on LOCA signal.

D Incorrect. no transfer to the UAT, EDGs do not start since ERAT is available.

System No:

KA No: RO: SRO: 262001 K4.06 3.6 3.9 System/Evolution:

A.C. Electrical Distribution Category Statement:

Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following:

K/A Statement:

Redundant power sources to vital buses Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 65 Question No:

ILT-0994 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None 3105.01, Turbine R35a Explanation:

A. Correct - Since the Main Turbine is < 75% the PMG is not in control. The Loss Of EHC 125 VDC power would result in a turbine trip.

B. Incorrect - turbine control valves fast close.

C. Incorrect - the turbine trips.

D. Incorrect - the turbine trips.

System No:

KA No: RO: SRO: 262002 K3.15 2.6 2.7 System/Evolution:

Uninterruptable Powe r Supply (A.C./D.C.)

Category Statement:

Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following:

K/A Statement:

Main turbine operation: Plant-Specific Cog Level:

Memory TIER: GROUP: 2 1 10CFR: CFR: 41.7 / 45.4

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 66 Question No:

ILT-4877 STA_Question RO Question SRO Question D Reference Provided:

Reference:

4979.01, Abnormal Release of Airborne Radioactivity R10a Explanation:

D is correct, 0RIX-PR012 is in operation, enter Abnormal Release of Airborne Radioactivity. RED Tile implies HIGH Alarm. 0RIX-PR001 in High Alarm starts 0RIX-PR012.

A is incorrect, 0RIX-PR012 is in operation, enter Abnormal Release of Airborne Radioactivity.

B is incorrect, 0RIX-PR012 is in operation.

C is incorrect, enter Abnormal Release of Airborne Radioactivity.

System No:

KA No: RO: SRO: Generic 2.3.15 2.9 3.1 System/Evolution:

Category Statement:

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

K/A Statement:

Cog Level:

High TIER: GROUP: 3 10CFR: CFR: 41.12 /

43.4 / 45.9

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 67 Question No:

ILT-7150 STA_Question RO Question SRO Question

a. Reference Provided:

Reference:

None EOP Bases Explanation:

A. is correct EOP Technical Bases states that ECCS systems are not included in the "Preferred ATWS Systems" since they inject inside the shroud. The Tech Bases goes on to say that "injecting cold, unborated water inside the core shroud may cause a large power excursion." B. is incorrect, LPCS can help supply sufficient flow.

C. is incorrect, LPCS can help maintain sufficient D/P.

D. is incorrect, dilution is accounted for.

System No:

KA No: RO: SRO: Generic 2.4.18 3.3 4 System/Evolution:

Emergency Procedures / Plan Category Statement:

Knowledge of the specific bases for EOPs K/A Statement:

Cog Level:

Memory TIER: GROUP: 10CFR: CFR: 41.10 /

43.1 / 45.13

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 68 Question No:

ILT-2133 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None EP-AA-1000 R 19 Explanation:

B is correct, the Station Emergency Director would have command authority from the TSC A is incorrect, the Shift Manager would have command authority from the Main Control Room C is incorrect, the TSC Director reports to the Station Emergency Director D is incorrect, the Corporate Emergency Director would have command authority from the EOF System No:

KA No: RO: SRO: Generic 2.4.37 3 4.1 System/Evolution:

Category Statement:

Knowledge of the lines of authority during implementation of the emergency plan.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: CFR: 41.10 /

45.13 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 69 Question No:

ILT-7136 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None ODCM 2.3.6 R 21a Explanation:

C is correct, CCW pressure is hi gher than WS pressure and will leak into WS with the result ant radioactive release to the environment.

A is incorrect, with CCW leaking into WS there will no t be any increase in Hx fouling.

B is incorrect, with CCW leaking into WS there will not be any increase demineralizer resin depletion.

D is incorrect, CCW expansi on tank level will decrease.

System No:

KA No: RO: SRO: 400000 K1.01 3.2 3.3 System/Evolution:

Component Cooling Water System (CCWS)

Category Statement:

Knowledge of the physical connections and / or cause-effect relationships between CCWS and the following:

K/A Statement:

Service water system Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.2 to 41.9 /

45.7 to 45.8

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 70 Question No:

ILT-7112 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 3214.01, CCW R24d Explanation:

C. Correct - Because the compressors would trip on high discharge air temperature due to the loss of CCW. The near instantaneous rupture of the system and subsequent trip of the CC pumps would result in the loss of cooling water flow and pressure to the compressors and their subsequent trip on high discharge air temperature.

A. Incorrect - Because the compressors would trip on discharge air temperature before the low lube oil pressure trip would occur.

B. Incorrect - The loss of cooling water pressure is just an alarm and no longer a signal to trip the compressors.

D. Incorrect - The loss of CCW will not effect seal temperatures.

System No:

KA No: RO: SRO: 300000 A3.02 2.9 2.7 System/Evolution:

Instrument Air System (IAS)

Category Statement:

Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including:

K/A Statement:

Air temperature Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.7 / 45.7

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 71 Question No:

ILT-7147 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 3506.01, Diesel Generator R 33 Explanation:

B is correct, raising the governor setpoint will give the D/G more fuel and it will pickup more real load (Amps) but speed will not change.

A is incorrect, raising the governor setpoint will give the D/G more fuel and it will pickup more real load (Amps)

C is incorrect, raising the governor setpoint will give the D/G more fuel and it will pickup more real load (Amps) but speed will not change.

D is incorrect, raising the governor setpoint will give the D/G more fuel and it will pickup more real load (Amps) but speed will not change.

System No:

KA No: RO: SRO: 264000 A1.03 2.8 2.9 System/Evolution:

Emergency Generators (Diesel/Jet)

Category Statement:

Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEL/JET) controls including:

K/A Statement:

Operating voltages, currents, and temperatures Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.5 / 45.5

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 72 Question No:

ILT-7113 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None USAR 8.3.2.1.2 Explanation:

C is correct, negative Amps and low Voltage shows the Div 2 battery is discharging. Div 4 indicates a normal condition with the battery on a Float charge.

A is incorrect, negative Amps and low Voltage shows the Div 2 battery is discharging.

B is incorrect, negative Amps and low Voltage shows the Div 2 battery is discharging.

D is incorrect, Div 4 indicates a normal condition with the battery on a Float charge.

System No:

KA No: RO: SRO: 263000 A4.03 2.7 2.8 System/Evolution:

D.C. Electrical Distribution Category Statement:

Ability to manually operate and/or monitor in the control room:

K/A Statement:

Battery discharge rate: Plant-Specific Cog Level:

High TIER: GROUP: 2 1 10CFR: CFR: 41.7 /

45.5 to 45.8

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 73 Question No:

ILT-5808 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

None CPS No. 4200.01, Loss Of AC Power Explanation:

C. Correct. Load shedding is a timely action.

A. Incorrect. Must be started within one hour. Not required if there is an ac source available powering the battery chargers for the associated dc bus.

B. Incorrect. Must be started within one hour D. Incorrect. Not required if there is an ac source available powering the battery chargers for the associated dc bus.

System No:

KA No: RO: SRO: 263000 2.4.11 4 4.2 System/Evolution:

D.C. Electrical Distribution Category Statement:

Knowledge of abnormal condition procedures.

K/A Statement:

Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.1/43.5/45.13

ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 74 Question No:

ILT-7114 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None 3314.01E001, SLC Electrical Lineup R 9a Explanation:

A is correct AB MCC 1B1 is the power supply to the B SLC Pump.

B is incorrect, CRD Drive Water Pump 1B is powered from 4160 V Bus 1B.

C is incorrect, RWCU Recirculation Pump 1B is powered from AB MCC 1E.

D is incorrect, Cycled Condensate Pump 1B is powered from 480V Unit Sub 1K.

System No:

KA No: RO: SRO: 211000 K2.01 2.9 3.1 System/Evolution:

Standby Liquid Control System Category Statement:

Knowledge of electrical power supplies to the following:

K/A Statement:

SBLC pumps Cog Level:

Memory TIER: GROUP: 2 1 10CFR: CFR: 41.7 ANSWER KEY ILT 08-01 RO ILT 08-01 NRC RO Exam Exam Question Number 75 Question No:

ILT-7138 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 3505.03, RAT & ERAT SVC R 6 Explanation:

B is Correct - Refer to CPS 3505.03, Section 8.3 and Appendix A. The + MVARs indication means that the SVC is acting to raise voltage. When the SVC is removed from service, the resulting (uncompensated) voltage will ramp down to 4,140 volts. The rule of thumb is 20 volts per MVAR. In this case, that amounts to -80 volts, or a FINAL value of 4,140 volts.

A Incorrect - Plausible to the candidate who either, does not recall the rule of thumb (applies 40 volts per MVAR instead of 20 volts per MVAR), or cannot distinguish between a + MVAR reading and a - MVAR reading.

C Incorrect - Plausible to the candidate who either, does not recall the rule of thumb (applies 40 volts per MVAR instead of 20 volts per MVAR), or cannot distinguish between a + MVAR reading and a - MVAR reading.

D Incorrect - Plausible to the candidate who either, does not recall the rule of thumb (applies 40 volts per MVAR instead of 20 volts per MVAR), or cannot distinguish between a + MVAR reading and a - MVAR reading.

System No:

KA No: RO: SRO: 262001 2.1.20 4.6 4.6 System/Evolution:

A.C. Electrical Distribution Category Statement:

Ability to interpret and execute procedure steps.

K/A Statement:

Cog Level:

High TIER: GROUP: 2 1 10CFR: CFR: 41.10 /

43.5 / 45.12

ILT 08-01 NRC RO Exam Question Number 1 Plant conditions are as follows:

50% power 5006-3D, OPRM Enabled alarm annunciates.

"1B" Reactor Recirculation Pump trips, and APRM power is fluctuating between a low value of 30.0% and a high value of 45.0% every 2 seconds.

WHICH ONE of the following describes what action(s) is/are required?

A: Insert a manual Reactor scram.

B: Attempt to restart the "1B" Reactor Recirculation Pump.

C: Reduce power by 5%, and then check magnitude of the APRM fluctuations.

D: Reduce power with control rods and verify NOT within the CONTROLLED ENTRY REGION of the Power/Flow Map.

Page 1 ILT 08-01 NRC RO Exam Question Number 2 The plant was initially operating at 92% power when an inadvertent group 1 isolation occurred.

Very little rod motion occurred on the subsequent scram.

Neither manual scram nor ARI were successful.

Both SLC pumps were started at 10:05.

What is the FIRST opportunity that a cooldown is allowed to be started?

A: As soon as the reactor becomes subcritical.

B: At time 10:45.

C: At time 11:25.

D: At time 11:35 if all rods are in.

Page 2 ILT 08-01 NRC RO Exam Question Number 3 The following plant conditions exist:

- A steam leak exists in the Turbine Building

- EOP-9, Radioactivity Release Control, has been entered.

- Turbine Building Ventilation has tripped.

What is the required operational response to the Turbine Building Ventilation trip and its basis?

A: Restart ventilation to prevent an unmonitored release.

B: Restart ventilation to lower the radioactive release.

C: Maintain ventilation tripped to lower the radioactive release.

D: Maintain ventilation tripped to prevent an unmonitored release.

Page 3 ILT 08-01 NRC RO Exam Question Number 4 The plant is at rated power with a normal electrical lineup and the MDRFP tagged out when a plant transient results in the following:

- First: the control power is lost for the ERAT breaker to Bus 1B1.

- Next: a RAT lockout occurs.

- Now: RPV level is -55 inches and lowering.

WHICH of the following describes the expected status of the safety related electrical distribution system?

A: All three DGs running, all three safety related busses powered from the DGs.

B: All three DGs running, busses 1A1 and 1C1 are powered from the ERAT. Bus 1B1 is powered from its DG.

C: Division 2 and 3 DGs are running, busses 1A1 and 1C1 are powered from the ERAT. Bus 1B1 is powered from its DG. D: Division 2 and 3 DGs are running, busses 1B1 and 1C1 are powered from their DGs. Bus 1A1 is powered from the ERAT. Page 4 ILT 08-01 NRC RO Exam Question Number 5 The following plant conditions exist:

- The reactor scrammed due to closure of the MSIVs.

- Suppression Pool temperature is 145F

- Suppression Pool level is 18.0 feet Which one of following approximates the highest allowed reactor pressure without exceeding the Heat Capacity Limit (Figure P)?

A: 650 psig B: 750 psig C: 850 psig D: 950 psig Page 5 ILT 08-01 NRC RO Exam Question Number 6 Plant conditions are as follows:

The Reactor is at 76% Rated Thermal Power.

- Drywell pressure is currently 0.9 psig and trending up at 0.05 psig/min.

- Drywell Temperature is 115°F and trending up at 0.5°F/min.

One minute after Drywell pressure started to rise, all Fission Product Monitor channels started rising.

Which ONE of the following problems would give this indication?

A: Small Feedwater leak in the Drywell.

B: Instrument Air leakage into the Drywell.

C: Small steam leak in the Drywell.

D: Failure of Drywell Cooling.

Page 6 ILT 08-01 NRC RO Exam Question Number 7 Which of the following describes the impact/consequence of a loss of the Component Cooling Water System (CC)?

A: The Condenser Vacuum pumps lose cooling and automatically trip, but can be restored with Shutdown Service Water supplying cooling.

B: The Fuel Pool Cooling and Cleanup System pumps and heat exchangers lose cooling and are NOT available until CC is restored.

C: The Service Air Compressors lose cooling and trip, but can be restored with Turbine Building Closed Cooling Water supplying cooling.

D: The Reactor Recirculation Pump motor windings and seals lose cooling which requires the RR Pumps to be stopped. Page 7 ILT 08-01 NRC RO Exam Question Number 8 A plant transient has occurred and the following conditions exist:

Drywell pressure is 2.3 psig slowly rising Reactor water level is -150" slowly lowering The 138 KV line is lost.

Division 1A DG has an over crank condition.

What are the power supplies available to the RHR pumps:

A B&C RHR RHR A: RAT RAT & Diesel Generator B: RAT RAT & ERAT C: ERAT & Diesel Generator ERAT & Diesel Generator D: RAT & Diesel Generator RAT Page 8 ILT 08-01 NRC RO Exam Question Number 9 The plant is in Mode 4 with RHR "A" in shutdown cooling, reactor water level momentarily drops to +5".

Both SDC suction isolation valves(1E12-F008/F009)-

A: remain open and the "A" RHR pump trips on low RPV level.

B: close and "A" RHR pump trips on low suction pressure.

C: close and the "A" RHR pump trips on low RPV level.

D: close and "A" RHR pump trips when either valve leaves its full open seat.

Page 9 ILT 08-01 NRC RO Exam Question Number 10 The plant is in a Refueling Outage moving irradiated fuel in the Spent Fuel Pool. The fuel handling operator moving the Fuel Handling Platform has a spent fuel bundle on the grapple. The bundle is NOT raised high enough to clear the fuel rack when the trolley starts moving. The spent fuel bundle becomes slightly bent causing a large bubble to rise from the bundle. The Fuel Handling Platform Area Radiation Monitor alarms.

Which one of the following describes actions to be taken and their reason?

A: Shift Containment Continuous Purge to the filtered mode to minimize the radioactive release to the environment.

B: Place bundle in safe condition and evacuate the Fuel Building to prevent overexposure to fission products released into the Fuel Building atmosphere.

C: Move the fuel bundle to the Inclined Fuel Transfer System in preparation to move it back to Containment to limit release of radioactive material into the Fuel Building.

D: Isolate the Containment to prevent any airborne radiation from leaving the Containment and have the Refueling Floor Radiation Protection Technician sample for airborne radioactivity .

Page 10 ILT 08-01 NRC RO Exam Question Number 11 The plant is at rated power.

Refer to the annunciator and PPC displays shown on the attached TWO (2) figures.

Which of the following actions must be performed?

A: Trip both Reactor Recirc Pumps.

B: Place the Mode Switch in Shutdown.

C: Restart both Reactor Recirc Hydraulic Power Units.

D: Lockout both Reactor Recirc Hydraulic Power Units.

Page 11 ILT 08-01 NRC RO Exam Question Number 12 A Group 1 Isolation occurred while at full power. The resultant transient lifted several Safety-Relief Valves. After these valves close, at what pressure will the next Safety-Relief Valve(s) open and WHY?

A: 1103 psig; to minimize cycling of the other SRVs.

B: 1033 psig; to prevent reaching the high pressure scram setpoint.

C: 1033 psig; to mitigate the effects of pressure loads on the containment.

D: 1103 psig; to mitigate the effects of pressure loads on the containment.

Page 12 ILT 08-01 NRC RO Exam Question Number 13 An emergency depressurization is required per EOP-6, "Primary Containment Control," when suppression pool temperature CANNOT be maintained below the Heat Capacity Temperature Limit (Figure P).

This ensures initiation of RPV depressurization will NOT result in exceeding -

A: Pressure Suppression Pressure.

B: Boron Injection Initiation Temperature.

C: Primary Containment Temperature Limit.

D: Net Positive Suction Head limits for low pressure ECCS.

Page 13 ILT 08-01 NRC RO Exam Question Number 14 Given the following conditions:

• A LOCA has occurred

• The reactor has been scrammed

• Reactor Pressure is 200 psig

• Drywell Temperature is 310°F

• Containment Temperature is 280°F

• Narrow Range Water Level indication is 13 inches

• Wide Range Water Level indication is -36 inches

• Upset Range Water Level indication is 28 inches Based on the current plant conditions, which of the following would be valid/invalid RPV water level indications?

Narrow Range Wide Range Upset Range A: valid valid valid B: valid valid invalid C: invalid valid valid D: valid invalid invalid Page 14 ILT 08-01 NRC RO Exam Question Number 15 Which one of the following Drywell Temperatures is the highest that would NOT require a Tech Spec entry?

A: 135°F B: 145°F C: 155°F D: 165°F Page 15 ILT 08-01 NRC RO Exam Question Number 16 EOP-6 requires a Blowdown if Suppression Pool Level CANNOT be held above 15 ft 1 inch irrespective of Suppression Pool Temperature.

Why? A: The ECCS pumps will lose suction.

B: A LOCA will challenge primary containment integrity.

C: A blowdown will chall enge drywell integrity.

D: The decrease in radioactive gas scrubbing will result in elevated radiation releases.

Page 16 ILT 08-01 NRC RO Exam Question Number 17

• A seismic event has occurred resulting in a DBA LOCA.

• The plant has scrammed

• The 'A' Recirculation Pump fails to trip.

Reactor level quickly lowers and indicates:

- Shutdown Range 1 inch

- Upset Range 0 inches

- Narrow Range 3 inches

- Wide Range -160" - Fuel Zone Range -112" What is the status of determining actual vessel level?

A: Can ONLY be determined using Fuel Zone since it is qualified to function under Post-LOCA conditions.

B: Can be determined. ALL instruments are AVAILABLE with Fuel Zone being the only one on scale.

C: Can be determined. ONLY the Shutdown, Upset, and Narrow Range should be used.

D: Can NOT be determined with these conditions.

Page 17 ILT 08-01 NRC RO Exam Question Number 18 The plant was operating at 92% power when all Station AC busses de-energize.

The following actions occur:

Reactor scrams.

Main Turbine Trips.

All attempts to start the Emergency Diesel Generators (EDGs) fail.

Load dispatcher reports that the offsite power outage is expected to last eight (8) hours.

Reactor water level control is established with RCIC and Reactor pressure is controlled with SRVs.

One (1) hour after the loss of AC occurs, DC load shedding is initiated and completed 45 minutes later.

What is the impact of the above conditions?

A: RCIC will become unavailable due to a loss of the Gland Seal Air Compressor.

B: RCIC system will become unavailable due to a high Lube Oil temperature before AC power is restored.

C: RCIC and SRVs will become unavailable due to a loss of DC power before battery chargers are restored.

D: Main Control Room area temperatures will exceed the habitability limit of 120°F due to loss of ventilation.

Page 18 ILT 08-01 NRC RO Exam Question Number 19 The Division 1 battery will supply the DBA loads (with coincident AC power loss) for a MINIMUM of __________ to maintain a cell voltage above its design value.

A: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D: 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Page 19 ILT 08-01 NRC RO Exam Question Number 20 A grid disturbance has resulted in the loss of a large industrial manufacturing facility.

The plant is operating at rated power with a normal plant lineup.

The Operator takes actions to return the Switchyard voltage to the specified band.

Why are the circulating water pumps drawing more current now than when the large manufacturing facility was on line?

A: The circulating water pump motor excitation went up.

B: The circulating water pump motor excitation went down.

C: The Generator VAR Loading lowers.

D: The Generator VAR Loading rises.

Page 20 ILT 08-01 NRC RO Exam Question Number 21 Plant conditions are as follows:

- Reactor power is 24%.

- Reactor Recirculation pumps are in slow speed.

- The MDRFP is Tagged Out.

- "A" TDRFP is in service.

- Condenser vacuum is slowly degrading.

As condenser vacuum degrades, which ONE of the following will occur FIRST?

A: Turbine Bypass Valve closure.

B: Reactor scram from MSIV closure.

C: Reactor scram from Main Turbine trip.

D: Reactor Recirculation System Runback signal.

Page 21 ILT 08-01 NRC RO Exam Question Number 22 Per CPS 4100.01, Reactor Scram, what is the target value operators lower Reactor pressure to in order to minimize the Feedwater-to-RPV Differential Temperature?

A: 1000 psig B: 800 psig C: 600 psig D: 400 psig Page 22 ILT 08-01 NRC RO Exam Question Number 23 The plant was initially operating at 92% power when a Main Control Room evacuation was required. The reactor was shutdown at 10:00 and the Remote Shutdown Panel (RSP) was manned. At 10:30 the following plant conditions exist:

- RCIC is in service with suction from the RCIC Storage Tank and discharge to the RCIC Storage Tank

- RCIC flow is 550 gpm

- Reactor Water level is 35 inches and steady

- RHR A is in Suppression Pool Cooling

- Suppression pool temperature is 100ºF

- Suppression pool level is 19.1ft

- RCIC storage tank level is 326" - Reactor pressure is 550 psig and lowering What is required?

A: Reduce RCIC flow.

B: Increase RCIC flow.

C: Maintain RCIC flow at 550 gpm.

D: Shift RCIC suction to the suppression pool.

Page 23 ILT 08-01 NRC RO Exam Question Number 24 The plant was at near rated power when a LOCA occurred. The following plant conditions exist:

-All Control Rods are fully inserted.

-Reactor Pressure is 200 psig.

-Reactor Water Level is -145 inches on Wide Range and slowly rising.

-The Reserve Auxiliary Transformer has Locked out.

-The only ECCS pumps that will run are LPCI A and B.

-LPCI A is injecting at maximum.

-LPCI B is in Suppression Pool Cooling.

-Containment Pressure is 3.0 psig.

-Containment Temperature is 180°F and rising.

In order to maintain containment integrity under these conditions the mitigating strategy is to-A: Initiate ONE loop of Containment Spray only.

B: Initiate BOTH loops of Containment Spray.

C: Vent the containment.

D: Lineup Shutdown Service Water to spray the Containment.

Page 24 ILT 08-01 NRC RO Exam Question Number 25 An ATWS has occurred. CPS procedure 4411.08, ALTERNATE CONTROL ROD INSERTION is being used to perform manual control rod insertion.

Why must the Rod Pattern Controller (RPC) be defeated and how is this accomplished?

A: ATWS rod positions may not match rod pattern in RCIS. The Turbine First Stage Pressure trip setpoint is set at minimum. B: ATWS rod positions may not match rod pattern in RCIS. The Turbine First Stage Pressure trip setpoint is set at maximum. C: Position indication to Rod Pattern Controller may be lost due to scram. The Turbine First Stage Pressure trip setpoint is set at minimum.

D: Position indication to Rod Pattern Controller may be lost due to scram. The Turbine First Stage Pressure trip setpoint is set at maximum.

Page 25 ILT 08-01 NRC RO Exam Question Number 26 The plant is in Mode 5.

Preparations are in progress to remove the Steam Dryer.

A loss of Instrument Air occurs.

Which of the following would be the expected result?

A: The Polar Crane Main Hook upward movement is prevented.

B: The Dryer Pool will leak into the Vessel Pool through the Gate seals.

C: The Dryer and Vessel Pool levels will remain the same.

D: The Fuel Pool Cooling and Cleanup Pumps will trip.

Page 26 ILT 08-01 NRC RO Exam Question Number 27 "B" Loop of RHR is in the Shutdown Cooling (SDC) mode.

The following conditions exist:

- RPV pressure is 65 psig.

- 4.16 KV Bus 1B1 trips and locks out.

- RPV pressure rises to 115 psig.

- No operator actions have been taken.

(1) Select the statement below that describes the expected response of 1E12-F009, Inboard Shutdown Cooling Suction Isolation valve?

(2) What actions are required?

A: (1) 1E12-F009 will isolate.

(2) Verify the B RHR pump is stopped.

B: (1) 1E12-F009 will isolate.

(2) Align and start A RHR pump.

C: (1) 1E12-F009 will NOT isolate.

(2) Verify reactor coolant circulation by an alternate method.

D: (1) 1E12-F009 will NOT isolate.

(2) Dispatch an operator to isolate SDC.

Page 27 ILT 08-01 NRC RO Exam Question Number 28 The plant is operating at 25% power.

The plant is scrammed and the B Reactor Recirc pump is shutdown and isolated due to a seal leak.

What is the SHORT TERM effect of isolating CRD from the B Recirc pump?

A: Drywell floor drain flow will drop.

B: B RR pump seal temperatures will drop.

C: Drywell airborne activity will rise.

D: The seal upper wear ring will drop.

Page 28 ILT 08-01 NRC RO Exam Question Number 29 The plant is operating at rated conditions.

The following plant conditions exist:

10:00 Fuel building exhaust radiation levels are 6 mr/hr.

10:15 Fuel building exhaust radiation levels are 8 mr/hr and rising at a constant rate.

What would be the operational implications if the radiation levels were allowed to continue to rise without operator action at 12:00?

A: Primary Containment integrity would be lost.

B: Secondary Containment integrity would be lost.

C: Fuel Building area temperatures would rise.

D: Ground level radiation release would approach release limits.

Page 29 ILT 08-01 NRC RO Exam Question Number 30 Which of the following describes CRD System response and the potential consequence of a Reactor SCRAM occurring with the Local Flow Control Valve Controller in MANUAL and the Main Control Room Flow Controller in AUTO?

A: The Flow Control Valve will close in response to increased charging header flow, resulting in insufficient cooling water flow.

B: The Flow Control Valve will open in response to increased cooling header flow, resulting in potential CRD pump runout. C: The Flow Control Valve will NOT close in response to increased charging header flow, resulting in insufficient cooling water flow.

D: The Flow Control Valve will NOT close in response to increased charging header flow, resulting in potential CRD pump runout.

Page 30 ILT 08-01 NRC RO Exam Question Number 31 AB MCC 1A3 is de-energized, which ONE of the following valves is affected?

A: LPCS INJECTION VALVE, 1E21-F005.

B: RCIC INJECTION VALVE, 1E51-F013.

C: HPCS INJECTION VALVE, 1E22-F004.

D: RHR "C" MINIMUM FLOW VALVE, 1E12-F064C.

Page 31 ILT 08-01 NRC RO Exam Question Number 32 The reactor has just scrammed from rated conditions.

A negative reactor period is observed.

Normal rod position indication from 1H13-P680 is unavailable.

RPS can NOT be reset.

RACC Panels 1H13-P651 and 1H13-P652 "all rods full in" LED is NOT lit.

For these plant conditions shutdown criteria__________.

A: is determined by use of either RACC panel by stepping thru the ID generator.

B: is determined by depressing DATA MODE pushbutton to select alternative display information.

C: is determined by using the process computer (OD-7 option 2 or 4).

D: is NOT able to be determined.

Page 32 ILT 08-01 NRC RO Exam Question Number 33 The plant is at rated power.

Number three (3) jet pump flow indication fails down scale.

Which ONE of the following indications would validate the down scale failure of number three (3) jet pump flow?

A: "A" loop driving flow lowers by 5 percent "B" loop driving flow raises by 5 percent Core flow remain unchanged.

B: "A" loop driving flow lowers by 10 percent "B" loop driving flow raises by 10 percent Core flow remain unchanged.

C: "A" loop driving flow remain unchanged "B" loop driving flow remain unchanged Core flow lowers 25 percent.

D: "A" loop driving flow remain unchanged "B" loop driving flow remain unchanged Core flow lowers 5 percent.

Page 33 ILT 08-01 NRC RO Exam Question Number 34 Given the following conditions:

- RHR A is in suppression pool cooling.

- The equalizing valve for an RHR A flow transmitter vibrates fully open.

Actual total flow to the suppression pool will _(1)_ and total cooling to the s uppression pool will _(2)_ .

A: (1) remain the same (2) lower B: (1) lower (2) remain the same C: (1) lower (2) lower D: (1) remain the same (2) rise Page 34 ILT 08-01 NRC RO Exam Question Number 35 The plant is operating at rated power.

Primary Containment pressure is -0.1 psig.

The Primary Containment pressure is being controlled by modulating the . . .

A: Containment Building Ventilation exhaust flow from Containment.

B: Containment Building Ventilation supply air flow into Containment.

C: Continuous Containment Purge exhaust flow from Containment.

D: Continuous Containment Purge supply air flow into Containment.

Page 35 ILT 08-01 NRC RO Exam Question Number 36 The plant is at rated power when 6.9 KV bus 1A trips.

Which of the following would be directly affected as a result of the bus trip?

A: Motor Driven Reactor Feed Pump.

B: The #1 Service Air Compressor.

C: The 1A Reactor Recirc Pump.

D: The "A" Drywell Chiller.

Page 36 ILT 08-01 NRC RO Exam Question Number 37 The extraction steam feed to the Steam Seal Evaporator Extraction Steam Non-return Check Valves, 1GS001 and 1GS002, are considered critical and are exercised daily. All other Extraction Steam Non-return Check Valves are exercised weekly.

Why? A: The Steam Seal Evaporator produces high pressure steam.

B: All other Extraction Steam lines have Motor operated shutoff valves.

C: The extraction steam feed to the Steam Seal Evaporator could feed Main Steam directly to the Main Turbine.

D: All other Extraction Steam lines have large enough drain lines to depressurize the lines directly to the condenser.

Page 37 ILT 08-01 NRC RO Exam Question Number 38 The plant is operating at rated power with all systems and equipment available.

No Condensate Polisher operations are in progress.

The Min Flow valve for a running Condensate Pump fails open.

Of the following:

(1) which annunciator(s) on P680 would be expected to alarm?

(2) which describes the procedure directed operator actions required to mitigate the situation?

A: (1) Low Pressure Rx FD Pumps Suction HDR (2) Place the Mode Switch in Shutdown B: (1) Low Pressure Rx FD Pumps Suction HDR (2) Start the standby Condensate Pump C: (1) Low Pressure Rx FD Pumps Suction HDR AND Tripped RFPT 1A Turbine (2) Place the Mode Switch in Shutdown D: (1) Low Pressure Rx FD Pumps Suction HDR AND Auto start of the RFP 1C (2) Start the standby Condensate Pump Page 38 ILT 08-01 NRC RO Exam Question Number 39 The plant is operating at 95% of Rated Thermal Power with both Turbine Driven Reactor Feed Pump (TDRFPs) in service. Narrow range level instrument, C34-N004A, is failed high.

Feedwater Level Control is selected to the "B" level instrument C34-N004B.

Narrow range level instrument C34-N004C suddenly fails high.

Which ONE of the following is the response of the feedwater system?

A: The TDRFPs trip.

B: The MDRFP starts and controls reactor water level.

C: The TDRFPs continue to control level since level instrument C34-N004B is selected.

D: The TDRFP flow controllers shift to MANUAL and Reactor water level response depends on feed and steam flow mismatch. Page 39 ILT 08-01 NRC RO Exam Question Number 40 The plant is in a normal full power lineup.

The following MCR AIR INTAKE r adiation monitor FAILURES occur:

- 'HI FAIL' on the 'D' monitor.

- 'AC POWER FAIL' on the 'C' monitor.

What will be the effect on the Control Room HVAC System?

A: VC will stay in the normal system lineup.

B: The Supply Air Filter Package will startup.

C: The Makeup Air Filter Package will shutdown.

D: VC will shift to the Purge mode of operation.

Page 40 ILT 08-01 NRC RO Exam Question Number 41 What is the normal method of maintaining the fire protection system pressurized with normal system leakage?

A: Continuous running of the Jockey Pump B: Intermittent running of the Jockey Pump C: Operation of the Horizontal Fire Pump D: Operation of a Diesel Fire Pump Page 41 ILT 08-01 NRC RO Exam Question Number 42 The plant is at rated power.

The annunciator shown on the "stem figure" alarms on panel P801.

Which figure on the choices page shows the proper line up for Control Room Ventilation Supply Air Filter due to the annunciator?

A: Figure A B: Figure B C: Figure C D: Figure D Page 42 ILT 08-01 NRC RO Exam Question Number 43 The plant was operating at 30% power.

A small break LOCA has occurred.

Mode switch is in shutdown.

Shut down criteria is met.

Drywell pressure is 2.0 psig and rising.

Reactor water level is -10 inches and lowering.

RCIC is injecting at 700 gpm.

Reactor pressure is 850 psig and lowering.

HPCS injection valve F004 has failed shut.

All other systems are operating as designed.

Which of the following statements describes the next action(s) required to maintain adequate core cooling?

A: Lower reactor pressure and use condensate and condensate booster pumps to restore reactor water level.

B: Initiate steam cooling.

C: Emergency depressurize to inject with low pressure systems.

D: Inhibit ADS.

Page 43 ILT 08-01 NRC RO Exam Question Number 44 The operator took both SLC control switches to RUN and RELEASED. Two minutes later the operator observed the following light indications. Both pumps responded as designed.

Using the attached figure for Question 44, determine which ONE of the following describes the expected status of the Standby Liquid Control (SC) system.

A: Both SLC pumps injecting through one squib valve.

B: Only one SLC pump injecting through squib valve B.

C: Only one SLC pump injecting through squib valve A.

D: NO SLC pump is injecting into the reactor vessel.

Page 44 ILT 08-01 NRC RO Exam Question Number 45 A plant startup is in progress, with the following:

- Reactor power is 85%

- Control rod withdrawals are complete

- Power ascension to rated power is in progress using Reactor Recirculation, only

- Approved and targeted ramp rate is 10% per hour (1) Who must be present in the Control Room?

(2) Who is allowed to perform the reactivity management function?

A: (1) Reactor Engineer (2) Control Room Supervisor B: (1) Shift Manager (2) Reactor Engineer C: (1) Reactor Engineer (2) Reactor Engineer D: (1) Shift Manager (2) Control Room Supervisor Page 45 ILT 08-01 NRC RO Exam Question Number 46 An operable motor operated valve (MOV) has been manually seated.

Which ONE of the following describes (1) A source to find the valve's physical location?

(2) The method to be used the next time the valve must be unseated?

A: (1) The system procedure valve lineup.

(2) Electrically with the handswitch.

B: (1) Passport.

(2) Electrically with the handswitch.

C: (1) The system procedure valve lineup.

(2) Manually.

D: (1) Passport.

(2) Manually.

Page 46 ILT 08-01 NRC RO Exam Question Number 47 The Reactor Coolant Chloride Limit is _(1)_ in Mode 1 than it is in Modes 2 and 3 because oxygen concentration is _(2)_ in Mode 1 than it is in Modes 2 and 3.

A: (1) Higher (2) Higher B: (1) Higher (2) Lower C: (1) Lower (2) Lower D: (1) Lower (2) Higher Page 47 ILT 08-01 NRC RO Exam Question Number 48 From the following, which statement describes "Operable-Operability", in accordance with CPS Technical Specifications.

The condition of a system, subsystem, division, component, or device-A: necessary to protect the integrity of certain physical barriers to guard against the uncontrolled release of radioactivity.

B: capable of performing its specified safety function with its support systems capable of performing their required support functions.

C: capable of performing its specified safety function with some of its support systems inoperable.

D: that will allow testing, calibration or inspection to assure operation is within Safety Limits and LCOs.

Page 48 ILT 08-01 NRC RO Exam Question Number 49 Annuciator 5060-8E, DIESEL GENERATOR 1A TROUBLE, has an orange flag on it.

Which ONE of the following describes the status of Annuciator 5060-8E?

A: Out of service annunciator.

B: Partially disabled annunciator.

C: Fully disabled annunciator.

D: Flagged as an expected alarm.

Page 49 ILT 08-01 NRC RO Exam Question Number 50 Plant is operating at 20% power.

"A" APRM fails upscale. In addition to the "A" APRM upscale light-(1) What is the impact of this failure?

(2) What is required to clear the alarm(s)?

(1) (2)

A: Div 1 Half scram only Bypass LPRMs on "A" APRM drawer B: Rod out block Place Division 1 sensor bypass switch in bypass AND Div 1 Half scram C: Rod out block Place Division 1 sensor bypass switch in bypass AND CRT White data "A" APRM D: Rod out block Bypass LPRMs on "A" APRM drawer AND CRT White data "A" APRM Page 50 ILT 08-01 NRC RO Exam Question Number 51 The Intermediate Range Monitors are calibrated such that a reading of 100 on range 10 corresponds to ________ Rated Thermal Power.

A: .04% B: .4% C: 4% D: 40% Page 51 ILT 08-01 NRC RO Exam Question Number 52 WHICH of the following Source Range Monitor (SRM) components are powered from the 120 VAC NSPS busses?

A: Detector drive motor controls B: High voltage power supplies C: Detector drive motors D: SRM recorders Page 52 ILT 08-01 NRC RO Exam Question Number 53 Predict the impact of the following plant conditions

- Mode 2 - an equipment fault causes Reactor Power to rise to 17%

(1) What is the impact on RPS?

(2) What action is required Next?

A: (1) NO RPS trip.

(2) Lower recirculation flow.

B: (1) RPS trip.

(2) Place the mode switch in shutdown.

C: (1) NO RPS trip.

(2) Insert Control Rods in reverse sequence.

D: (1) RPS trip.

(2) Place the Mode switch in RUN.

Page 53 ILT 08-01 NRC RO Exam Question Number 54 With the reactor at normal operating pressure which of the following is the LOWEST tail pipe temperature that would be an indication of a fully opened Safety Relief Valve?

A: 270°F B: 390°F C: 420°F D: 450°F Page 54 ILT 08-01 NRC RO Exam Question Number 55 The unit was operating in normal, full power lineup.

- A small break LOCA occurred, dropping RPV water level to -52 inches.

- HPCS and RCIC started and raised RPV water level to Level 8.

- Current RPV water level is 30 inches and is lowering at 2 inches/minute.

- RCIC has been placed in normal injection lineup for RPV water level and RPV pressure control.

- RCIC Storage Tank level instruments fail low.

Assuming NO additional operator actions are performed which ONE of the following automatic actions will occur next?

A: RCIC overspeed trips.

B: RCIC suction transfers.

C: HPCS injection valve opens.

D: HPCS minimum flow valve opens.

Page 55 ILT 08-01 NRC RO Exam Question Number 56 The plant is in Mode 5 with the Reactor Mode Switch in REFUEL.

Fuel movement is in progress and the shorting links are removed.

What is the consequence of SRM "D" failing upscale?

A: Full scram with a rod block.

B: Full scram NO rod block.

C: Half scram with a rod block D: Half scram NO rod block.

Page 56 ILT 08-01 NRC RO Exam Question Number 57 The following condition exists pertaining to the APRMs

- Sensor Bypass switches are in Normal

- 17 LPRMs bypassed in channel "C" - 18 LPRMs bypassed in channel "D" - APRM "B" AGAF is 0.95 APRM channel "A" is deenergized due to a fault inside the APRM drawer.

What is the effect, if any, of the above conditions?

A: Reactor automatically scrams immediately.

B: Reactor remains critical but a Rod Withdrawal Block is initiated.

C: Reactor automatically scrams after the OPRMs reach 20 counts.

D: No automatic actions but Technical Specifications actions are required.

Page 57 ILT 08-01 NRC RO Exam Question Number 58 An Equipment Operator is to perform a clearance that requires independent verification.

Which ONE of the following components could be eligible for an independent verification waiver?

A Danger tag to be hung on the-A: 1G33-F043A, RT Pump A suction isolation valve, handwheel.

B: 1CO01T CO2 compressor disconnect switch.

C: breaker for 1WS002A at Screenhouse MCC 1A.

D: 1CP-MV1A condensate polisher A inlet valve control switch at 1PL03J, TB 712.

Page 58 ILT 08-01 NRC RO Exam Question Number 59 (1) Which RHR Loop is the preferred loop for Shutdown cooling in mode 4?

(2) Why? A: (1) A (2) Less tubes are plugged in the A Heat Exchanger B: (1) A (2) Can discharge to Radwaste remotely C: (1) B (2) Less tubes are plugged in the B Heat Exchanger D: (1) B (2) Can discharge to Radwaste remotely Page 59 ILT 08-01 NRC RO Exam Question Number 60 Plant conditions are as follows:

The Reactor is at Rated Power.

A DIV 1 NSPS circuit malfunction causes the INPUT to the Load Driver that services Group 8 isolation valves to fail to ZERO.

Which ONE of the following valves shuts as a result of this failure?

A: REACTOR CORE ISOLATION COOLING CO NTAINMENT INBOARD VALVE, 1E51F063.

B: EQUIPMENT DRAIN SUMP DISCHARGE CONTAINMENT OUTBOARD VALVE, 1RE022.

C: REACTOR WATER CLEANUP SUCTION OUTBOARD ISOLATION VALVE, 1G33F004 D: CONTAINMENT BUILDING SUPPLY INBOARD ISOLATION BYPASS VALVE, 1VR002B.

Page 60 ILT 08-01 NRC RO Exam Question Number 61 The plant is operating at rated power when SRV F051G fully opens.

No operator actions are performed.

Which of the following describes an expected response for the first TEN (10) minutes after the SRV opens?

A: Rx power rises and stabilizes at a higher value.

B: Rx water level rises and stabilizes at a higher value.

C: Rx water level lowers and stabilizes at a lower value.

D: MW electrical lowers and then returns to its previous value.

Page 61 ILT 08-01 NRC RO Exam Question Number 62 The plant is operating at 60% power with both Turbine Driven Reactor Feed Pumps (TDRFP) on the Master Level Controller.

The D area operator reports the "A" Reactor Feed Pump (RFP) is noisy and "rougher" than the "B" pump.

A short time later the vibration readings on the "A" Reactor Feed Pump begin to go up and MCR Annunciator 5002 window 3B "High Vibration RFP 1A Shaft" alarms.

What direction would you expect from the CRS?

A: Reduce reactor power to less than 35% and place RFP's Flow Controllers on the Startup Controller.

B: Shift the "A" RFP to the Startup Controller and open the pump Minimum Flow Valve 1FW010A.

C: Transfer "A" RFP Flow Controller to MANUAL and reduce turbine speed.

D: Press TURB A pushbutton on the Start Mode Actuator Selector switch for automatic control of "A" RFP.

Page 62 ILT 08-01 NRC RO Exam Question Number 63 Containment Continuous Purge Exhaust Radiation reads 120 mR/hr.

What is the expected status of the following?

Fuel Building Standby Gas Treatment Exhaust Isolation System Accident Range Damper 1VF09Y. Monitor (AXM), 0RIX-PR008.

A: SHUT RUNNING B: SHUT IN STANDBY C: OPEN RUNNING D: OPEN IN STANDBY Page 63 ILT 08-01 NRC RO Exam Question Number 64 Given the following plant conditions:

- Plant at 92% power.

- 6.9 KV and 4.16 KV Non ECCS Electrical Busses powered by the UAT.

- 4.16 KV ECCS Electrical Busses Powered by the RAT.

- No abnormal line-ups exist in the electrical distribution system.

The expected automatic response of the electrical distribution system to a loss of the RAT is that the 4.16KV ECCS busses ____________________.

A: load shed and are re-energized by the EDGs.

B: load shed then transfer to the ERAT, EDGs do NOT start.

C: auto transfer to the ERAT, NO load shedding occurs, EDGs do NOT start.

D: auto transfer to the UAT, NO load shedding occurs, EDGs start but do NOT tie to the bus.

Page 64 ILT 08-01 NRC RO Exam Question Number 65 A Main Turbine startup is in progress.

The Main Turbine speed is 1300 rpm and rising A loss of 1B UPS bus occurs.

What effect, if any, will this have on the Main Turbine Generator?

A: The Main Turbine trips.

B: All turbine control valves ramp close.

C: No effect on the Main Turbine.

D: The Main Turbine overspeeds.

Page 65 ILT 08-01 NRC RO Exam Question Number 66 On the AR/PR Display, the Common Station HVAC Exhaust Stack Monitor, 0RIX-PR001 indicating tile is RED due to a trip of channel 5 (Low Range Noble Gas).

The Accident Range HVAC Monitor, 0RIX-PR012 should be in _(1)_.

If it is verified that the RED indication is NOT due to a spike, it is immediately required to enter _(2)_.

A: (1) standby (2) EOP-9, Radioactivity Release Control B: (1) standby (2) Abnormal Release of Airborne Radioactivity, 4979.01 C: (1) operation (2) EOP-9, Radioactivity Release Control D: (1) operation (2) Abnormal Release of Airborne Radioactivity, 4979.01 Page 66 ILT 08-01 NRC RO Exam Question Number 67 Which of the following explains why EOP-1A ATWS RPV Control lists Low Pressure Core Spray(LPCS) as an alternate rather than a preferred injection source to flood the RPV during an ATWS?

A: LPCS could cause power excursions since it injects inside the shroud.

B: LPCS does NOT have the required flow rate to assure adequate core cooling during the floodup.

C: LPCS CANNOT maintain the required 198 psid with five SRVs opened that is needed to assure adequate core cooling. D: The SLC boron concentration requirement of technical specifications assumes that NO systems are injecting inside the shroud and diluting the mixture.

Page 67 ILT 08-01 NRC RO Exam Question Number 68 Plant conditions warrant declaration of Emergency Classification at the SITE AREA EMERGENCY level. From the following, choose who would have Command Authority from the Technical Support Center (TSC) after Command Authority has been transferred to the TSC.

A: Shift Emergency Director B: Station Emergency Director C: TSC Director D: Corporate Emergency Director Page 68 ILT 08-01 NRC RO Exam Question Number 69 The plant is in MODE 5 for a refueling outage, with the following:

- Shutdown Service Water (SX) Pumps A and C are out-of-service and have Clearances installed.

- THEN, a complete loss of Service Water (WS) occurs.

- SX Pump B starts and runs.

- The associated WS to SX Header Isolation Valve fails to FULLY close.

- NLO reports that SX Header Pressure reads 90 psig, locally.

- THEN, a tube leak occurs in the inservice CCW Heat Exchanger.

Which ONE of the following describes the POTENTIAL consequence of the CCW HX tube leak?

A: Reduced heat transfer due to heat transfer surface fouling B: Higher rate of depletion of the CCW Demineralizer resin C: Radioactive discharge to the environment D: Rising level in the CCW Expansion Tank Page 69 ILT 08-01 NRC RO Exam Question Number 70 The plant was operating at 95% Rated Thermal Power when a very large pipe rupture occurred in the Component Cooling (CCW) System and resulted in the instantaneous loss of the CCW system.

Which ONE of the following parameters provides the FIRST signal to trip the SA/IA Compressors?

A: Lube oil pressure.

B: Cooling water pressure.

C: Discharge air temperature.

D: Seal temperature.

Page 70 ILT 08-01 NRC RO Exam Question Number 71 A diesel generator (D/G) is supplying an electrical bus in parallel with the grid. If the D/G governor setpoint is raised for two seconds, then D/G Output Frequency will be __(1)__ and D/G Output Current will be __(2)__.

A: (1) the same (2) the same B: (1) the same (2) higher C: (1) higher (2) higher D: (1) higher (2) the same Page 71 ILT 08-01 NRC RO Exam Question Number 72 The plant is operating at rated conditions.

The attached figure shows the status of the Div 2 and Div 4 DC busses.

Which one of the following describes the status of the Batteries?

Div 2 is __(1)__

Div 4 is __(2)__

A: (1) on a Float Charge (2) Discharging B: (1) on a Float Charge (2) early in an Equalize Charge C: (1) Discharging (2) on a Float Charge D: (1) Discharging (2) early in an Equalize Charge Page 72 ILT 08-01 NRC RO Exam Question Number 73 A Station Blackout (SBO) has occurred.

The HPCS Pump is injecting.

Which of the following actions are required?

DC load shed shall-A: NOT be started until one hour after a SBO has occurred and shall be performed on ALL four DC busses.

B: NOT be started until one hour after a SBO has occurred and shall be performed ONLY for those DC busses that have lost the associated AC busses.

C: be performed within the first hour after a SBO has occurred and shall be performed ONLY for those DC busses that have lost the associated AC busses.

D: be performed within the first hour after a SBO has occurred and shall be performed on ALL four DC busses.

Page 73 ILT 08-01 NRC RO Exam Question Number 74 Aux Building MCC 1B1 is deenergized.

The component that loses power is-A: SLC Pump 1B B: CRD Drive Water Pump 1B C: RWCU Recirculation Pump 1B D: Cycled Condensate Pump 1B Page 74 ILT 08-01 NRC RO Exam Question Number 75 The plant is in a normal full power lineup.

The RAT SVC readings at P870 are as follows:

4,220 Volts

+4 MVARs Which ONE of the following will be the FINAL Div 1 Bus voltage AFTER the operator places the RAT SVC control switch to OFF?

A: 4,060 Volts B: 4,140 Volts C: 4,300 Volts D: 4,380 Volts Page 75 CLINTON 2009 ILE Written Examination Answer Key RO: SRO:

Q# Answer Q# Answer Q# Answer Q# Answer 1 A 26 C 51 D 1 B 2 B 27 C 52 B 2 D 3 A 28 C 53 B 3 C 4 C 29 C 54 B 4 C 5 B 30 D 55 B 5 A

6 C 31 A 56 A 6 C 7 D 32 A 57 A 7 C 8 A 33 D 58 A 8 A 9 D 34 A 59 D 9 C 10 B 35 D 60 B 10 D

11 D 36 C 61 A 11 B 12 C 37 C 62 C 12 A 13 C 38 B 63 A 13 B 14 B 39 A 64 C 14 B 15 B 40 B 65 A 15 C

16 B 41 B 66 D 16 A 17 D 42 B 67 A 17 C 18 C 43 A 68 B 18 D 19 B 44 A 69 C 19 D 20 C 45 A 70 C 20 B 21 D 46 D 71 B 21 D 22 C 47 B 72 C 22 C 23 A 48 B 73 C 23 B 24 A 49 B 74 A 24 A 25 A 50 C 75 B 25 C

RO EXAM PROVIDED

REFERENCES:

1. CPS No. 4003.01, Remote Shutdown, Table 1, Rev. 2/23/1999, Saturated Temperature/Pressure Correlation

Question #11 Figure 1 of 2

Question #11 Figure 2 of 2 1.1+2.0+0.0 35.0 1023.9 72.9 -0.1 96 +0.5+0.0 +0.0-0.00 -999 Question 42 Stem Figure

Question 42 Figure A Choices Page Figure B

Figure C Figure D Question #44

Question #72

SRO EXAM PROVIDED

REFERENCES:

1. EP-AA-1003, Rev. 14, Radiological Emergency Plan Annex (NO ENTRY CONDITIONS or BASES) 2. OU-CL-104, Rev. 002, Shutdown Safety Management Program

3. Technical Specification 3.5.1

4. Technical Specification 3.8.3

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 1 Question No:

ILT-6583 STA_Question RO Question SRO Question B Reference Provided:

Reference:

Technical Specifications 3.8.3 TS 3.8.1, 3.8.3, 3.0.4 Explanation:

B. Correct - The low starting air pressure Div 1B DG requires it to be declared inoperable and all three DG are required to be operable to change to Mode 1, IAW TS 3.0.4.

A. Incorrect - Div I DG remains operable.

C. Incorrect - Transfer to mode 1 is not allowed.

D. Incorrect - Div 2 DG is inoperable and transfer to mode 1 is not allowed.

This is a Tech Spec determination which meets 10CFR 55.43.2 System No:

KA No: RO: SRO: 295003 2.2.42 3.9 4.6 System/Evolution:

Partial or Complete Loss of A.C. Power Category Statement:

Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

K/A Statement:

Cog Level:

High TIER: GROUP: 1 1 10CFR: CFR: 41.7 /

41.10 / 43.2 /

43.3 / 45.3

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 2 Question No:

ILT-6380 STA_Question RO Question SRO Question D Reference Provided:

Reference:

None EOP-1 R 27 Explanation:

D is correct, an automatic scram should have occurred so action must be taken to manually scram the reactor and the NRC must authorize restart.

A. An automatic scram should have occurred so action must be taken to manually scram the reactor.

B. An automatic scram should have occurred so action must be taken to manually scram the reactor C. The NRC must authorize restart.

A normal plant startup must be authorized by the Plant Manager. This makes A and C plausible This is a Tech Spec application which meets 10CFR 55.43.2 System No:

KA No: RO: SRO: 295005 AA2.05 3.8 3.9 System/Evolution:

Main Turbine Generator Trip Category Statement:

Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:

K/A Statement:

Reactor power Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 3 Question No:

ILT-2139 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

EP-AA-1003, Radiological Emergency Plan Annex For Clinton CPS 4003.01, Remote Shutdown R 14b Explanation:

C is correct, A Site Area Emergency must be declared due the inability to establish plant control within 15 minutes.

A is incorrect, A Site Area Emergency must be declared due the inability to establish plant control within 15 minutes.

B is incorrect, the Alert is incorrect due to the inability to establish plant control.

D is incorrect, A Site Area Emergency must be declared due the inability to establish plant control within 15 minutes.

E-plan classification is an SRO function.

System No:

KA No: RO: SRO: 295016 2.4.41 2.9 4.6 System/Evolution:

Control Room Abandonment Category Statement:

Knowledge of the emergency action level thresholds and classifications.

K/A Statement:

Cog Level:

High TIER: GROUP: 1 1 10CFR: 41.10 / 43.5 /

45.11 ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 4 Question No:

ILT-4922 STA_Question RO Question SRO Question C Reference Provided:

Reference:

EP-AA-1003 CL3-6 to 3-13; Full set of EOPs with Entry EP-AA-1003 14 Conditions and Cautions blanked.

Explanation:

C is correct, spike only requires a confirming sample, the value is in excess of Alert value per RA1, this is an EOP-9 entry condition.

A is wrong, EOP-9 entry.

B is wrong, spike only requires a confirming sample, the value is in excess of Alert value per RA1, this is an EOP-9 entry condition.

D is wrong, spike only requires a confirming sample.

This requires the assessment of conditions using the E-Plan Classifications and selection of a procedure as per 10CFR55.43.4 System No:

KA No: RO: SRO: 295017 2.4.4 4.5 4.7 System/Evolution:

High Off-Site Release Rate Category Statement:

Ability to recognize abnormal indications for system operating parameters that are entry-lev el conditions for emergency and abnormal operating procedures.

K/A Statement:

Cog Level:

High TIER: GROUP: 1 2 10CFR: 41.10 / 43.2 /

45.6 ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 5 Question No:

ILT-7117 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None CPS No. 4001.02, Automatic Isolation, section 4.5 Explanation:

A is correct, CPS No. 4001.02, Automatic Isolation, section 4.5, -within 3 hrs start/verify running SLC System. Per ITS Bases, the SLC sys is also used to maintain suppression pool pH at or above 7 following a LOCA involving significant fission product release.

B is incorrect, Aux Seal Injection Pump will shunt trip on Level 1 or Hi DW press.

C is incorrect, Not within the "OK TO SPRAY" region of Figure O.

D is incorrect, Containment press too hi to use VG on Cnmt.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 295019 2.4.21 4 4.6 System/Evolution:

Partial or complete loss of Instrument Air Category Statement:

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, lradioactivity release control, etc.

K/A Statement:

Cog Level:

High TIER: GROUP: 1 1 10CFR: CFR: 41.7 /

43.5 / 45.12

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 6 Question No:

ILT-7119 STA_Question RO Question SRO Question C Reference Provided:

Reference:

OU-CL-104 Rev 2 OU-CL-104 Rev 2 Explanation:

Correct Answer C is correct. Per CPS OU-CL-104, Section 4.4.4, RWCU cannot be 'counted' as an available alternate DHR method, when assessing Shutdown Risk Level, until a calculation is performed to show that RWCU is capable of handling the current decay heat load. Therefore, per CPS OU-CL-04, Attachment 2 (for MODE 4), the only CURRENTLY available decay heat removal method is 'ECCS feed and bleed through the SRVs'. A review of the same Attachment (right-most column), shows that the CURRENT Shutdown Risk Level is, therefore, RED. The 'Orange' distracters are plausible to the examinee who neglects to consider the guidelines of Section 4.4.4; that examinee will likely 'count' RWCU as being CURRENTLY available, and conclude that the risk level is Orange. A review of CPS 4006.01, Loss of SDC, Table 2 (NOTE) shows that ECCS feed/ble ed through the SRVs is NEVER a PREF ERRED lineup for alternate decay heat removal. Given a choice between the only two viable methods (RWCU and ECCS-SRVs), the RWCU lineup is PREFERRED.

Distracters a, b, and d are incorrect for reasons as stated above.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 295021 2.1.20 4.6 4.6 System/Evolution:

Loss of Shutdown Cooling Category Statement:

Ability to interpret and execute procedure steps.

K/A Statement:

Cog Level:

High TIER: GROUP: 1 1 10CFR: CFR: 41.10 /

43.5 / 45.12 ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 7 Question No:

ILT-7146 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None Tech Spec Bases Explanation:

C is correct, as pool level rises the loads on the bottom of the floor above the pool during a LOCA increase and becomes a reason for limiting pool level A is incorrect, containment wall loading is not is not a concern but SRV tail pipe loading is.

B is incorrect, Pool level does not limit hydrogen mixer capacity.

D is incorrect, RCIC exhaust pressure will increase with pool level but is not limiting.

System No:

KA No: RO: SRO: 295029 2.2.25 3.2 4.2 System/Evolution:

Equipment Control Category Statement:

Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 2 1 10CFR: CFR: 41.5 /

41.7 / 43.2

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 8 Question No:

ILT-7145 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None CPS 4007.02 Inadvertent Rod Movement Revision 12e Explanation:

A. Correct. From CPS 4007.02 Inadvertent Rod Movement a symptoms of Annunciators 5005-3J IRM downscale and 5006-4G Rod Drift are received with a negative period. All three groups Reactor Engineer, Chemistry and Radiation Protection, must be notified.

B. Incorrect. Power is dropping and therefore a Rod Drop has not happened.

C. Incorrect. All three groups Reactor Engineer, Chemistry and Radiation Protection, must be notified.

D. Incorrect. Power is dropping and therefore a Rod Drop has not happened.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 295014 AA2.02 3.9 3.9 System/Evolution:

Inadvertent Reactivity Addition Category Statement:

Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION :

K/A Statement:

Reactor period Cog Level:

High TIER: GROUP: 1 2 10CFR: 41.10 / 43.5 /

45.13 ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 9 Question No:

ILT-7120 STA_Question RO Question SRO Question C Reference Provided:

Reference:

EOP-6 EOP-6 Primary Containment Control R 28 Explanation:

c. Correct - CPS 4402.01, EOP-6; in the POOL TEMPERATURE section, "Cannot hold pool temperature below the Heat Capacity Limit, Fig P." If Reactor pressure was lower a blowdown would not be required

a. Incorrect - Level is still high enough that other methods should be attempted first.

b. Incorrect - Containment pressure is stable and spraying would remove more water from a suppression pool with lowering level.

d. Incorrect - Group 1 Isolation has occurred, this action will not depressurize the Reactor.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 295026 EA2.03 3.9 4 System/Evolution:

Suppression Pool High Water Temperature Category Statement:

Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

K/A Statement:

Reactor pressure Cog Level:

High TIER: GROUP: 1 1 10CFR: CFR: 41.10 /

43.5 / 45.13

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 10 Question No:

ILT-6385 STA_Question RO Question SRO Question D Reference Provided:

Reference:

EOP-6 EOP-6, Primary Containment Control R 28 Explanation:

D is correct answer, EOP-6 states to keep trying to lower temperature with VR/VQ.

A is incorrect, not at a point yet in EOP-6 & EOP-1 to Blowdown.

B is incorrect, would only Flood if water level was unknown, and Containment & Drywell temperatures are not that high yet. C is incorrect, containment Sprays would not be used because RHR pumps are required for core cooling.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 295027 EA2.01 3.7 3.7 System/Evolution:

High Containment Temperature (Mark III Containment Only)

Category Statement:

Ability to determine and/or interpret the following as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY):

K/A Statement:

Containment temperature: Mark-III Cog Level:

High TIER: GROUP: 1 1 10CFR: CFR: 41.10 /

43.5 / 45.13

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 11 Question No:

ILT-6064 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 3703.01, Core Alterations R 26 Explanation:

B is correct, If not released move to the correct location per the move sheets and initiate an issue report A is incorrect, do not release the bundle.

C is incorrect, complete the move per the move sheets.

D is incorrect, complete the move per the move sheets then contact the R.E.

Refer to CPS 3703.01, Section 6.24.1. This question proposes that exact scenario.

Requires knowledge of fuel handling procedures per 10CFR55.43.7 System No:

KA No: RO: SRO: 234000 2.1.32 3.8 4 System/Evolution:

Fuel Handling Category Statement:

Ability to explain and apply system limits and precautions.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 2 2 10CFR: CFR: 41.10 /

43.2 / 45.12

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 12 Question No:

ILT-3454 STA_Question RO Question SRO Question

a. Reference Provided:

Reference:

None 3105.01, Turbine R 35a Explanation:

A. Correct - section 2.4 "loss of Lube Oil" is defined as an emergency. 8.3.6 requires vacuum broken.

B. Incorrect - An emergency exists.

C. Incorrect - Vacuum should be broken.

d. Incorrect - An emergency exists, vacuum should be broken.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 245000 A2.02 3.3 3.5 System/Evolution:

Main Turbine Generator and Auxiliary Systems Category Statement:

Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

Loss of lube oil Cog Level:

Memory TIER: GROUP: 10CFR: CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 13 Question No:

ILT-7143 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 4009.01 Inadvertent Opening SRV R 11d Explanation:

B is correct, one SRV passes approximately 6.5% of total steam flow. The heat removal capacity of both RHR loops in suppression pool cooling is equivalent to approximately 1% of total steam flow. Therefore Suppression Pool temperature will continue to rise. The Inadvertent Opening SRV procedure directs the performance of a Rapid Plant Shutdown per Unit Power Changes.

A is incorrect, The Inadvertent Opening SRV procedure directs the performance of a Rapid Plant Shutdown per Unit Power Changes C is incorrect, one SRV passes approximately 6.5% of total steam flow. The heat removal capacity of both RHR loops in suppression pool cooling is equivalent to approximately 1% of total steam flow. Therefore Suppression Pool temperature will continue to rise.

D is incorrect, one SRV passes approximately 6.5% of total steam flow. The heat removal capacity of both RHR loops in suppression pool cooling is equivalent to approximately 1% of total steam flow. Therefore Suppression Pool temperature will continue to rise.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 239002 A2.03 4.1 4.2 System/Evolution:

Relief/Safety Valves Category Statement:

Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

Stuck open SRV Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 14 Question No:

ILT-7122 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None 3319.01, Standby Gas Treatment R 16 Explanation:

B is correct, the LOCA signals (Level 2/High DW Pressure) isolate VF and start both trains of VG. One train of VG must be shutdown to preserve a train for later operation.

A is incorrect, VF shuts down C is incorrect, Both trains of VG start D is incorrect, Both trains of VG start, VF should not be restarted unless EOP-8 is entered This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 288000 A2.02 3.4 3.6 System/Evolution:

Plant Ventilation Systems Category Statement:

Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEM S ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

Low reactor water level: Plant-Specific Cog Level:

High TIER: GROUP: 2 2 10CFR: CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 15 Question No:

ILT-7123 STA_Question RO Question SRO Question C. Reference Provided:

Reference:

T/S 3.5.1 Technical Specifications Explanation:

C. Correct answer based on technical specifications. 3.5.1 A.1 and D.1. Knowledge of the technical specification bases is required to determine LPCS operability.

A. Incorrect, LPCS is inop due to the loss of a support system (Room cooling).

B. Incorrect. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> applies if two ECCS subsystems are inop.

D. Incorrect. 14 days applies to HPCS inop.

This is a Tech Spec determination which meets 10CFR 55.43.2 System No:

KA No: RO: SRO: 209001 2.2.37 3.6 4.6 System/Evolution:

Low Pressure Core Spray System Category Statement:

Ability to determine operability and/or availability of safety related equipment.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 2 1 10CFR: 41.7/43.5/45.12

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 16 Question No:

ILT-4889 STA_Question RO Question SRO Question A Reference Provided:

Reference:

None 3309.01 HPCS R 16 Explanation:

A. A is correct, CPS 3309.01, step 4.3 requires pulling fuses with loss of fill and vent.

B. B is wrong, fill and vent is a required recovery action.

C. C is wrong, 1E22-F015 HPCS Suppression Pool Suction does not auto shut but 1E22-F001, HPCS Storage Tank Suction Valve does.

D. D is wrong, E22-F015 HPCS Suppression Pool Suction does not auto shut but 1E22-F001, HPCS Storage Tank Suction Valve does. Fill and vent is a required recovery action.

This requires the assessment of conditions and selection of a procedure section as per 10CFR55.43.5 System No:

KA No: RO: SRO: 209002 A2.10 2.7 3 System/Evolution:

High Pressure Core Spray System (HPCS)

Category Statement:

Ability to (a) predict the impacts of the following on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

Valve openings: BWR-5,6 Cog Level:

High TIER: GROUP: 2 1 10CFR: CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 17 Question No:

ILT-7125 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None 3703.01, Core Alterations R26 Explanation:

C is correct, as a minimum the Refuel Bridge Operator, Spotter and Refuel SRO must verify the in-core coordinates.

A is incorrect, as a minimum the Refuel Bridge Operator, Spotter and Refuel SRO must verify the in-core coordinates.

B is incorrect, as a minimum the Refuel Bridge Operator, Spotter and Refuel SRO must verify the in-core coordinates.

D is incorrect, the Reactor Engineer is not required.

Requires knowledge of fuel handling procedures per 10CFR55.43.7 Note ROs do not move fuel at CPS System No:

KA No: RO: SRO: Generic 2.1.36 3 4.1 System/Evolution:

Conduct of Operations Category Statement:

Knowledge of procedures and limitations involved in core alterations.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: CFR: 41.10 /

43.6 / 45.7

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 18 Question No:

ILT-6065 STA_Question RO Question SRO Question D Reference Provided:

Reference:

None OP-CL-101-102-1001 R 2 Explanation:

D is correct, in Modes 4 and 5, only 2 SROs are required (for ERO functions of CRS and SM), and no STA is required.

A is incorrect, need another SRO to cover the IA.

B is incorrect, Safe Shutdown Qualified Operator cannot be a Brigade Member.

C is incorrect, FOUR Fire Brigade Members are needed.

Requires knowledge of conditions and limitations in the facility license per 10CFR55.43.1 System No:

KA No: RO: SRO: Generic 2.1.5 2.9 3.9 System/Evolution:

Conduct of Operations Category Statement:

Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: CFR: 41.10 /

43.5 / 45.12

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 19 Question No:

ILT-7133 STA_Question RO Question SRO Question D. Reference Provided:

Reference:

None EP-AA-111 Emergency classification and protective Explanation:

D. Correct answer. 15 minutes after the event is declared a report must be made to the NRC and an Upgrade in the condition starts a new 15 minute clock event though that there is a 30 minute follow up reports are due on the less severe declaration.

A. Incorrect. 15 minutes for initial report.

B. Incorrect. 15 minutes for the SAE declaration.

C. Incorrect. 15 minutes for the SAE declaration.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: Generic 2.4.29 3.1 4.4 System/Evolution:

Emergency Procedures / Plan Category Statement:

Knowledge of the emergency plan.

K/A Statement:

Cog Level:

High TIER: GROUP: 3 10CFR: CFR: 41.10 /

43.5 / 45.11

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 20 Question No:

ILT-7128 STA_Question RO Question SRO Question B Reference Provided:

Reference:

None MA-AA-716-004, Conduct of Troubleshooting R 7 Explanation:

B is correct, the investigation is troubleshooting which is controlled by the Conduct of Troubleshooting procedure.

A is incorrect, ER-AA-10, Equipment Reliability defines the responsibilities for troubleshooting but does not control troubleshooting.

C is incorrect, 3105.01, Turbine (TG EHC TS) give the instructions for operating EHC but not troubleshooting it.

D is incorrect, 1070.01, Coordination Plans do not control work in the field.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: Generic 2.2.20 2.6 3.8 System/Evolution:

Equipment Control Category Statement:

Knowledge of the process for managing troubleshooting activities.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: CFR: 41.10 /

43.5 / 45.13

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 21 Question No:

ILT-7129 STA_Question RO Question SRO Question D. Reference Provided:

Reference:

None EP-AA-113 F-02 R B Explanation:

D. Correct. An Emergency Director is required to authorize emergency exposures and brief if greater than 25 REM. The stem indicates that 33.3 REM is expected for the rescue.

A. Incorrect. RP Technician assess the situation but NOT authorize emergency exposure or brief.

B. Incorrect. An Emergency Director is required to authorize emergency exposures and brief if greater than 25 REM.

C. Incorrect. The individuals must be fully aware of the risks involved "before the fact".

Requires assessment of radiation hazards per 10CFR55.43.4 System No:

KA No: RO: SRO: Generic 2.3.04 3.2 3.7 System/Evolution:

Radiation Control Category Statement:

Knowledge of radiation exposure limits under normal or emergency conditions.

K/A Statement:

Cog Level:

Memory TIER: GROUP: 3 10CFR: 41.12 / 43.4 /

45.10 ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 22 Question No:

ILT-7144 STA_Question RO Question SRO Question C Reference Provided:

Reference:

None Technical Specification Explanation:

C is correct with any head closure bolt not fully tensioned the plant is in MODE 5 as soon as all head closure bolts are fully tensioned with temperature >200 the plant will be in MODE 3 A is incorrect, due to a temperature of > 200 degrees F, a candidate may believe that we are in MODE 3, Hot Shutdown and may believe this is not affected by tensioning the head closure bolts.

B is incorrect, with the head closure bolts not fully tensioned, a candidate may expect that the condition would be considered MODE 4 (cold shutdown) and that it would change to MODE 3 (hot shutdown) when the bolts are tensioned to hold pressure.

D is incorrect, the candidate may recognize that the Unit is MODE 5, and believe that it will move to MODE 4 (cold shutdown) when the bolts are tensioned.

This is a Tech Spec determination which meets 10CFR 55.43.2 System No:

KA No: RO: SRO: Generic 2.2.35 3.6 4.5 System/Evolution:

Equipment Control Category Statement:

Ability to determine Technical Specification Mode of Operation.

K/A Statement:

Cog Level:

High TIER: GROUP: 3 10CFR: 41.7 / 41.10 /

43.2 / 45.13

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 23 Question No:

ILT-7131 STA_Question RO Question SRO Question B Reference Provided:

Reference:

EOP-1 CPS 4401.01, EOP-1 RPV CONTROL R 28 Explanation:

B is correct - Per EOP-1, RPV Control, Level leg requires the exiting of the EOPs and entering the SAGs if level can not be raised above -187 inches and hold it there.

A is incorrect, only allowed in EOP-1A before actuation, never allowed after actuation.

C is incorrect, not required unless RPV level cannot be determined.

D is incorrect, all EOPs are required to be exited.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: Generic 2.4.16 3.5 4.4 System/Evolution:

Emergency Procedures / Plan Category Statement:

Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

K/A Statement:

Cog Level:

High TIER: GROUP: 3 10CFR: CFR: 41.10 /

43.5 / 45.13

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 24 Question No:

ILT-3353 STA_Question RO Question SRO Question A. Reference Provided:

Reference:

EOP's EOP-1 Preferred injection systems Explanation:

A. Correct, RHR will trip on loss of a suction path, the operator should understand RPV level will lower and that EOP-1 RPV Control provides injection systems available to maintain level.

B Incorrect, RHR trips.

C Incorrect, EOP-3 BLOWDOWN is inappropriate until TAF.

D Incorrect, RHR trips, Level instruments are operable, EOP-2 RPV FLOOD unnecessary.

Note LPCS and HPCS due not trip on a loss of a suction path but RHR does.

This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 203000 A2.03 3.2 3.3 System/Evolution:

RHR/LPCI: Injection Mode Category Statement:

Ability to (a) predict the impacts of the following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

K/A Statement:

Valve Closures Cog Level:

High TIER: GROUP: 2 1 10CFR: 41.5 / 45.6

ANSWER KEY ILT 08-01 SRO ILT 08-01 SRO Exam Question Number 25 Question No:

ILT-7132 STA_Question RO Question SRO Question C Reference Provided:

Reference:

EOP-3 EOP-3, Emergency RPV Depressurization, R 28 Explanation:

C is correct, Feedwater must be terminated and prevented prior to the blowdown during an ATWS A is incorrect, ADS can be manually initiated while inhibited B is incorrect, the upper pools need to be dumped but not prior to the blowdown D is incorrect, RCIC and SLC can be left running This requires the assessment of conditions and selection of a procedure as per 10CFR55.43.5 System No:

KA No: RO: SRO: 218000 2.4.6 3.7 4.7 System/Evolution:

Automatic Depressurization System Category Statement:

Knowledge of EOP mitigation strategies.

K/A Statement:

Cog Level:

High TIER: GROUP: 2 1 10CFR: CFR: 41.10 /

43.5 / 45.13

ILT 08-01 SRO Question Number 1 Plant conditions are as follows:

- A Reactor startup is in progress.

- The Reactor Mode Switch is in STARTUP & HOT STBY.

- Reactor power is 8.0% with preparations being made to place the Reactor Mode Switch to RUN.

- The C Area just reported the Diesel Generator (DG) parameters:

Div 1A air receiver pressure 205 psig and stable fuel level 45,000 gal Div 1B air receiver pressure 115 psig and stable fuel level 45,000 gal Div 1C air receiver pressure 175 psig and stable fuel level 30,000 gal Evaluate the above conditions and determine:

(1) Diesel 1A, B, and C operability._____________

(2) The start up can ___________________

A: (1) ALL Division DG's are INOPERABLE.

(2) not continue, halt actions to place the Reactor Mode Switch to RUN.

B: (1) Diesel 1A&C OPERABLE, Division 1B INOPERABLE.

(2) not continue, halt actions to place the Reactor Mode Switch to RUN.

C: (1) Diesel 1B&C OPERABLE, Division 1A INOPERABLE.

(2) continue the power ascension including placing the Reactor Mode Switch to RUN.

D: (1) Diesel 1A&C OPERABLE, Division 1B INOPERABLE.

(2) continue the power ascension including placing the Reactor Mode Switch to RUN.

Page 1 ILT 08-01 SRO Question Number 2 The following annunciators have just been received:

5004-2D, DIV 1 OR 4 TCV FST CL TRIP 5005-2D, DIV 2 OR 3 TCV FST CL TRIP 5007-1B, TURB TRIP EHC SYS Current Reactor Power is 38%

(1) Which of the following actions must be directed?

(2) If this caused a MCPR Safety Limit violation operation of the unit shall not resume until authorized by the-A: (1) Perform a rapid plant shutdown (2) Plant Manager B: (1) Perform a rapid plant shutdown (2) NRC C: (1) Place the mode switch in Shutdown (2) Plant Manager D: (1) Place the mode switch in Shutdown (2) NRC Page 2 ILT 08-01 SRO Question Number 3 The Main Control Room is evacuated at 10:20 AM due to heavy smoke.

Control of shutdown systems from the remote shutdown panel is completed at 10:38 AM.

What is the classification?

A: Notification of Unusual Event B: Alert C: Site Area Emergency D: General Emergency Page 3 ILT 08-01 SRO Question Number 4 The plant is in Hot Shutdown with RHR Loop 'B' being placed into shutdown cooling.

SX Service Water Effluent B 1RIX-PR039 Alarmed High. A check of the monitor history showed it to be spiking.

With 1RIX-PR039 spiking it is required to _____(1)_____.

It is determined that a release has been in progress for 25 minutes at 210 X ODCM release rate limits.

Subsequent actions are governed by _____(2)_____.

A: (1) sample for a release (2) 4979.05, Abnormal Release of Radioactive Liquids B: (1) isolate RHR B (2) 4979.05, Abnormal Release of Radioactive Liquids C: (1) sample for a release (2) EOP-9, Radioactivity Release Control D: (1) isolate RHR B (2) EOP-9, Radioactivity Release Control Page 4 ILT 08-01 SRO Question Number 5 A total loss of Instrument Air has caused a reactor scram and MSIV closure.

Plant conditions are as follows:

- All control rods are fully inserted.

- Drywell Pressure is at 5.0 psig and steady.

- Drywell Temperature is at 222°F and steady.

- Containment Temperature is at 210°F and steady.

- Containment pressure is at 2.7 psig and steady.

- RPV pressure is at 50 psig and dropping due to performing a Blowdown because of low RPV water level.

Which of the following describes (1) an operator action that must be directed and (2) the reason for the action should these conditions remain unchanged for greater than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />?

A: (1) start/verify running the Standby Liquid Control System (2) to maintain suppression pool pH at or above 7 B: (1) start the Aux Seal Injection Pump (2) to maintain the integrity of the RR Pump seals C: (1) start Containment Sprays (2) to cool the Containment D: (1) start SBGT "A" or "B" on Primary Containment (2) to lower Containment pressure

Page 5 ILT 08-01 SRO Question Number 6 The plant is in MODE 4, preparing for an outage, with the following:

- Main condenser is opened for maintenance and is unavailable

- RHR Pump 'B' is tagged out for a motor replacement and is unavailable

- RHR Pump 'A' was running in Shutdown Cooling Mode trips and becomes unavailable

- Engineering is performing the RWCU decay heat removal calculation

- Reactor water level is 80 inches on shutdown range and stable

- All other plant systems are operable for MODE 4 Using procedure OU-CL-104 determine the following:

(1) Shutdown Risk Level for Decay Heat Removal?

(2) The decay heat removal method you would use NEXT?

A: (1) Orange (2) RWCU in a maximum cooling lineup B: (1) Orange (2) ECCS feed and bleed through the SRVs C: (1) Red (2) RWCU in a maximum cooling lineup D: (1) Red (2) ECCS feed and bleed through the SRVs Page 6 ILT 08-01 SRO Question Number 7 Which one of the following is a Tech Spec Bases for the Suppression Pool high water level limit?

Prevent excessive-A: containment wall loading during SRV operation.

B: reduction in Hydrogen mixing system capacity.

C: pool swell loads during an LOCA.

D: RCIC exhaust pressure.

Page 7 ILT 08-01 SRO Question Number 8 A RX startup is in progress with the following conditions:

- Below the point of adding heat.

- NO rod motion is currently being performed.

- Annunciator 5005-3J IRM downscale is received.

- Annunciator 5006-4G Rod Drift is received.

- One Rod Drift Light is energized.

- SRM 'A' shows a -100 sec. period.

(1) As the CRS which procedure should you enter?

(2) For the procedure entered who must be notified?

A: (1) CPS 4007.02 Inadvertent Rod Movement (2) Reactor Engineer, Chemistry and Radiation Protection B: (1) CPS 4007.03 Rod Drop (2) Reactor Engineer, Chemistry and Radiation Protection C: (1) CPS 4007.02 Inadvertent Rod Movement (2) Reactor Engineer ONLY D: (1) CPS 4007.03 Rod Drop (2) Reactor Engineer ONLY Page 8 ILT 08-01 SRO Question Number 9 Plant conditions are currently as follows:

Drywell temperature is 300 °F, stable.

Drywell pressure is 8.5 psig, rising at 0.1 psig/minute.

RPV water level is -142 inches (Wide Range), stable.

RPV pressure is 200 psig, lowering at 5.0 psig/minute.

Suppression Pool level is 18 feet 10 inches, lowering at 0.1 inch/minute.

Suppression Pool Temperature is 180 °F, rising at 1.0 °F/minute.*

Containment pressure is 1.3 psig, stable.

Containment temperature is 132°F, stable.

A Group 1 isolation is complete.

Which ONE of the following describes the next required operator action?

A: Dump upper pools.

B: Start containment sprays.

C: Perform a Reactor blowdown.

D: Rapidly depressurize the RPV using the main turbine bypass valves Page 9 ILT 08-01 SRO Question Number 10 The reactor has scrammed, and plant conditions are currently as follows:

Containment Pressure 2.0 psig Containment Temperature 175°F RPV water level is stable at -140 inches NO high pressure injection systems are available.

Operation of ALL low pressure Emergency Core Cooling Systems (ECCS) is required to maintain this RPV water level.

Which of the following actions has the highest priority?

A: Blowdown B: Flood the RPV C: Start Containment Sprays D: Start all available containment cooling Page 10 ILT 08-01 SRO Question Number 11 Core Alterations are in progress, with the following:

- A fuel bundle has been removed from the Upper Containment Fuel Storage Pool (UCP) per the move sheets.

- That same fuel bundle has just been placed in the core, BUT the grapple has NOT been released.

- THEN, the Refuel SRO recognizes the fuel bundle is NOT in its correct core location.

Which ONE of the following describes the NEXT required actions?

A: RELEASE the grapple and contact the Reactor Engineer for further guidance.

B: Remove the bundle from the core and place it in its CORRECT core location.

C: Remove the bundle from the core and return it to its UCP rack location.

D: RELEASE the grapple and update the move sheets.

Page 11 ILT 08-01 SRO Question Number 12 Plant conditions are as follows:

- The Reactor is at 90% power.

- TURB TRIP EHC SYS, 5007-1B annunciator alarms.

- The B RO reports that Bearing Oil Pressure reads 9 psig and is lowering.

- All equipment has responded as expected Concerning the Main Turbine, which one of the following is correct?

An Emergency Condition____(1)_____, the order shall be given to____(2)_____.

A: (1) exists (2) break vacuum B: (1) doesn't exist (2) break vacuum C: (1) exists (2) lower vacuum to 25 in. Hg D: (1) doesn't exist (2) lower vacuum to 25 in. Hg Page 12 ILT 08-01 SRO Question Number 13 The plant is near rated power when SRV 51G fails open.

All attempts to close SRV 51G have failed.

Both loops of Suppression Pool Cooling have been placed in service.

CCP has been shifted to the filtered mode of operation.

(1) What will Suppression Pool Temperature do?

(2) What procedure actions shall be performed next?

A: (1) Rise (2) Unit Power Changes Emergency Power Reduction B: (1) Rise (2) Unit Power Changes Rapid Plant Shutdown C: (1) Lower (2) Unit Power Changes Emergency Power Reduction D: (1) Lower (2) Unit Power Changes Rapid Plant Shutdown Page 13 ILT 08-01 SRO Question Number 14 Plant conditions are as follows:

- A DBA Loss Of Coolant Accident has occurred.

- All plant systems responded as designed.

EOP-1 and EOP-6 have been entered.

(1) What is the status of Fuel Building Ventilation and Standby Gas (VG)?

(2) What action(s) shall be directed?

A: (1) VF and both trains of VG are running.

(2) Shutdown one train of VG.

B: (1) VF is shutdown and both trains of VG are running.

(2) Shutdown one train of VG.

C: (1) VF and one train of VG are running.

(2) Start the second train of VG only.

D: (1) VF is shutdown and one train of VG is running.

(2) Shutdown VG and restart VF.

Page 14 ILT 08-01 SRO Question Number 15 The plant is operating at 90% Rated Thermal Power.

While performing CPS No. 9052.01, LPCS/RHR A PUMPS & LPCS/RHR A WATER LEG PUMP OPERABILITY, the LPCS pump room fan trips. It is determined to be a winding short requiring extensive repairs.

If a Technical Specifications action is required, what is the maximum time allowed?

A: No Technical Specification actions are required LPCS is OPERABLE.

B: Restore LPCS to operable with in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

C: Restore the LPCS system to operable in 7 days or be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

D: Restore the LPCS system to operable in 14 days or be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Page 15 ILT 08-01 SRO Question Number 16 Plant is at full power and High Pressure Core Spray (HPCS) valve testing is being performed.

The HPCS Pump, Trip and Close fuses were removed.

1E22-F001, HPCS Storage Tank Suction Valve is shut per the test procedure.

What impact will the following actions have on the HPCS system and what procedure required action(s) will be performed prior to replacing the Trip and Close fuses?

- 1E22-F023, HPCS Test Valve To Suppression Pool is opened then shut for valve stroke time testing.

- 1E22-F001, HPCS Storage Tank Suction Valve is opened.

A: HPCS system drains.

Fill and vent HPCS system.

B: HPCS system drains.

Verify suction pressure is returned to normal.

C: The 1E22-F015 HPCS Suppression Pool Suction shuts.

Fill and vent HPCS system.

D: The 1E22-F015 HPCS Suppression Pool Suction shuts.

Verify suction pressure is returned to normal.

Page 16 ILT 08-01 SRO Question Number 17 The plant is in a refueling outage with Core Alterations in progress.

The verification of in-core coordinates should be performed as a minimum by the:

A: Refuel Bridge Operator only.

B: Refuel Bridge Operator and Spotter only.

C: Refuel Bridge Operator, Spotter and Refuel SRO only.

D: Refuel Bridge Operator, Spotter, Refuel SRO and Reactor Engineer.

Page 17 ILT 08-01 SRO Question Number 18 Considering the MINIMUM staffing requirement for either the SROs, or Fire Brigade Members, which ONE of the following describes a situation that SATISFIES the respective requirement?

A: While in MODE 1, you have a total of TWO SROs, one of whom is BOTH the Shift Manager and IA, and the other is BOTH the Control Room Supervisor AND designated STA.

B: While in MODE 3, you have a total of FOUR Fire Brigade Members, one of whom is also the designated Safe Shutdown Qualified Operator.

C: While in MODE 5, you have a total of THREE Fire Brigade Members, ALL of whom are 'C Area Qualified'.

D: While in MODE 4, you have total of TWO SROs, NEITHER of whom is qualified as STA.

Page 18 ILT 08-01 SRO Question Number 19 You are the SRO in the control room when the following conditions exist:

10:05 Event for Alert occurred.

10:20 an Alert is declared.

11:00 Event for Site Area Emergency occurred.

11:15 a Site Area Emergency is declared.

What are the times by which the reports to the State and NRC must be made?

A: Alert State 10:50 Site Area Emergency State 11:30 NRC 11:20 NRC 12:00 B: Alert State 10:35 Site Area Emergency State 11:45 NRC 11:35 NRC 12:00 C: Alert State 10:35 Site Area Emergency State 11:45 NRC 11:05 NRC 12:15 D: Alert State 10:35 Site Area Emergency State 11:30 NRC 11:20 NRC 12:15 Page 19 ILT 08-01 SRO Question Number 20 The A Main EHC Pump is causing pressure oscillations.

An investigation into the cause is required.

What procedure is used to manage the investigation?

A: ER-AA-10, Equipment Reliability Process B: MA-AA-716-004, Conduct of Troubleshooting C: 3105.01, Turbine (TG EHC TS)

D: 1070.01, Coordination Plans Page 20 ILT 08-01 SRO Question Number 21 The plant is in Mode 5.

- A dropped fuel bundle causes dose rates of 200 Rem/hr on the refuel floor.

- During evacuation the spotter falls and breaks his leg.

- An emergency exposure is authorized to rescue the spotter.

- It will take 10 minutes to get the spotter off of the refuel floor.

Who is responsible for giving a radiological condition brief?

A: RP Technician B: TSC Director C: No one, its for life saving D: Station Emergency Director or Shift Manager Page 21 ILT 08-01 SRO Question Number 22 Given the following Conditions:

Reactor Mode Switch is in Shutdown.

Average Reactor Coolant Temperature is 205 degrees F.

Reactor Vessel Head closure bolt tensioning will be complete in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

The Unit is currently in _____(1)_____ and the _____(2)_____ must be completed prior to the completion of Reactor Vessel Head closure bolt tensioning.

A: (1) MODE 4 (2) cooldown to less than or equal to 200ºF B: (1) MODE 4 (2) MODE 3 Checklist C: (1) MODE 5 (2) MODE 3 Checklist D: (1) MODE 5 (2) MODE 4 Checklist Page 22 ILT 08-01 SRO Question Number 23 Following a major plant transient from rated power, the following plant conditions exist:

Reactor is shutdown with all rods in.

All Preferred Injection Systems have malfunctioned.

ADS was initiated when Reactor level dropped below -160 inches on Wide Range instruments.

Reactor pressure is at 55 psig, lowering at 10 psig/minute.

Several Alternate Injection Systems are lined up and injecting.

Reactor water level has trended from -200 inches to -269 inches over the last 10 minutes.

Which of the following describes the required operator action?

A: Initiate RPV Flooding, enter EOP-2, to flood to the Main Stream lines.

B: Initiate Primary Containment Flood, exit all EOP flowcharts and enter all SAG flowcharts.

C: Initiate Primary Containment Flood, enter all SAG flowcharts and continue actions in EOP-1 to raise RPV level.

D: Initiate additional pressure relief by opening more SRVs for core flooding. Restore the RFP 1C for injection.

Page 23 ILT 08-01 SRO Question Number 24 A LOCA has occurred, the appropriate procedures have been entered.

- Reactor Pressure is 2 psig.

- RHR A Pump is injecting at 5000 gpm.

- Reactor Water Level is stable at +10".

(1) Predict the impact of an RHR A suppression pool suction valve closure.

(2) Identify the procedure that should be used to correct the conditions.

A: (1) RHR A Pump trips (2) EOP-1 RPV CONTROL B: (1) RHR A Pump continues to run (2) EOP-6 PRIMARY CONTAINMENT CONTROL C: (1) RHR A Pump trips (2) EOP-3 BLOWDOWN D: (1) RHR A Pump continues to run (2) EOP-2 RPV FLOOD Page 24 ILT 08-01 SRO Question Number 25 A failure to scram has occurred.

The following conditions exist:

- ADS has been inhibited.

- SLC pump A is operating.

- Seven SRVs are operable and are being manually cycled for pressure control.

- MDRFP and RCIC are maintaining RPV level.

- Suppression pool level is 17.5 feet and lowering at 1 inch per 5 minutes.

Blowdown is required due to high Suppression pool temperature.

What action must be taken by the crew prior to blowdown?

A: ADS must be un-inhibited.

B: The upper pools must be dumped.

C: Feedwater injection must be terminated.

D: All injection (RCIC, Feed, & SLC) must be terminated.

Page 25