Text

SO-December 2003-Final RO Reference Exam
	ML040210270
Person / Time
Site:	San Onofre
Issue date:	01/29/2004
From:	; NRC Region 4
To:	;
References
	50-361/03-301, 50-362/03-301
	Download: ML040210270 (105)
	v • d • e

Question 1:

Given the following conditions:

Reactor Power 100%

Group 6 CEA 23 LEL is lit

Core mimic light for CEA 23 is lit

Tcold is 535ºF and lowering Which ONE (1) of the following actions should be taken in accordance with SO23-13-13, Misaligned Control Element Assembly?

Within 15 minutes of discovery initiate Rx Power reduction of 5% by A. inserting Part Length CEAs.

B. inserting Group 6 CEAs.

C. commencing RCS boration.

D. reducing turbine load using CVOL.

Answer: C.

Reference:

SO23-13-13, Misaligned or immovable Control Element Assembly Learning Objective: _________________________ (As available)

Question Source: Bank # _______

Modified Bank # _______

New __X__

Examination Outline Cross-reference: Level RO SRO K/A # 00005 AK3.05_ 000005 AK3.05_

Importance Rating _3.7_ _3.8_

Tier # __1__ __1__

Group # __1__ __1__

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _

10 CFR Part 55 Content: 55.41 _____

55.43 _____

Question 2 Given the following conditions:

Unit 3 operating at 100% full power.

Reactor Coolant Pump P004 has the following stable indications:

o Lower seal inlet pressure 2250 psia o Middle seal inlet pressure 585 psia o Middle seal outlet pressure 490 psia o Controlled Bleedoff flow 4.9 gpm o Lower seal inlet temperature 115º F o Middle seal inlet temperature 115º F o Middle seal outlet temperature 120º F Which ONE (1) of the following describes the status of the P004 seal system?

A. Lower Seal is degraded.

B. Middle Seal is degraded.

C. Upper Seal is degraded.

D. Component cooling water flow is degraded.

Answer: B

Reference:

SO23-12-1, LOSS OF COOLANT ACCIDENT Question Source: Bank # ___X__

Modified Bank # ___ ___

New __ __

Examination Outline Cross-reference: Level RO SRO K/A # 00015G2.1.28_ 000015G2.1.28_

Importance Rating _3.2_ _3.3_

Tier # __1__ __1__

Group # __1__ __1__

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis X_

10 CFR Part 55 Content: 55.41 _____

55.43 _____

Question 3 Given the following conditions:

The plant has been operating at 100% power for the past 4 weeks.

Letdown non-regenerative heat exchanger outlet temperature has DROPPED from 120ºF to 85ºF

At the end of your shift, you notice that Circulation water inlet temperature has DROPPED 5ºF.

Tcold has RISEN 3ºF

Generator KW output has RISEN 2 MW Which ONE (1) of the following best explains the changes in Tcold and Generator output?

A. The burnout of fuel has resulted in a decrease in positive reactivity of the core.

B. The Purification Ion Exchanger's increased absorption of boron has resulted in an inadvertent reactivity addition.

C. The lower circulating water injection temperature has resulted in reduced condenser pressure (better vacuum), which improved the efficiency of the generator.

D. The power operations have depleted burnable poisons at a faster rate than the fuel; this has resulted in a net increase in the positive reactivity in the core.

Answer: B

References:

Lesson Objective: 6551 Per the Emergency Boration of the RCS or Inadvertent Dilution/Boration procedure, SO23-13-11, The basis for each step, caution, or note.

The expected plant response for each step Question Source: Bank # ___ ___

Modified Bank # _______

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 0024AK1.02 0024AK1.02 Importance Rating 3.6 3.9 Tier # 1 1 Group # 1 1

Question 4 Given the following conditions:

Unit 2 is at 15% power with power ascension in progress.

Component Cooling Water (CCW) is lost to the Non Critical Loop.

It is determined that flow cannot be restored.

Which ONE (1) of the following actions is required per AOI SO23-13-7, Loss of CCW/SWC?

A. Trip the reactor and then secure the RCP(s).

B. Cross connect the component cooling water loops, perform a normal plant shutdown and then secure the RCP(s).

C. Perform a Rapid Plant Shutdown and then secure the RCP(s).

D. Cross connect the component cooling water loops, perform a Rapid Plant Shutdown and then secure the RCP(s).

Answer: A

References:

AOI SO23-13-7 Question Source: Bank # __ ___

Modified Bank # ___X __

New ___ _ .

Question Cognitive Level: Memory or Fundamental Knowledge _X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 000026AK3.03 000026AK3.03 Importance Rating 4.0 4.2 Tier # 1 1 Group # 1 1

Question 5 Given the following conditions:

The plant is at 100% Power.

Pressurizer Pressure Controller, 2PIC-100, is in Automatic.

All other Pressurizer pressure controls are in their normal configuration.

In preparation for maintenance, the second and third point Heaters E038 and E040 are bypassed.

All other systems respond as designed.

Consider only the effects of the above conditions on Pressurizer pressure.

Assuming no action by the crew, which ONE (1) of the following correctly describes the plant response?

A. There is an outsurge from the Pzr, the spray valves modulate open, steam in the Pzr will expand to mitigate the pressure transient, output from the proportional heaters will increase.

B. There is an insurge into the Pzr, the spray valves modulate shut, steam in the Pzr will condense to water to mitigate the pressure transient, output from the proportional heaters will decrease.

C. There is an insurge into the Pzr, the spray valves modulate open, steam in the Pzr will condense to water to mitigate the pressure transient, output from the proportional heaters will increase.

D. There is an outsurge from the Pzr, the spray valves modulate shut, water in the Pzr will flash to steam to mitigate the pressure transient, output from the proportional heaters will increase.

Answer: D.

References:

Question Source: Bank # __ __ __

Modified Bank # __ ____

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000027A1.02 000027A1.02 Importance Rating 2.8 3.1 Tier # 1 1 Group # 1 1

Question 6 Given the following conditions:

Unit 2 tripped due to an ESDE

SIAS, CIAS, and MSIS have actuated

SO23-12-5 Excessive Steam Demand is in progress

S/G E089 has blown dry

S/G E089 T-hot is 495º F and STABLE

S/G E089T-cold is 420º F and TRENDING UP

S/G E088 pressure is 700 psia and TRENDING DOWN

S/G E088 T-hot is 485º F and TRENDING DOWN

S/G E088 T-cold is 472º F and TRENDING DOWN

Pressurizer Pressure is 1800 psia and TRENDING UP

Pressurizer Level is 25% and TRENDING UP Which ONE (1) of the following indicates the target S/G pressure required to stabilize RCS temperature?

A. 310 psia B. 590 psia C. 525 psia D. 650 psia Answer: A

References:

SO23-12-5 Question Source: Bank # ___X___

Modified Bank # _______

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11 W/E08 EK2.2 CE/A11 W/E08 EK2.2 Importance Rating 3.6 4.0 Tier # 1 1 Group # 1 1

Question 7 Given the following conditions:

Reactor power is 10%.

A main turbine roll to 1800 rpm is in progress.

Condenser vacuum has begun degrading.

Annunciator 99B37, VACUUM LO is actuated.

Condenser Backpressure is 7 inches Hg absolute Which ONE (1) of the following immediate actions is required?

A. Reduce turbine speed to stabilize condenser vacuum.

B. Raise Tcold to reduce SBCS load.

C. Trip the turbine D. Observe the vacuum trend over the next five (5) minutes to determine if the turbine must be tripped.

Answer: C.

References:

Question Source: Bank # ___X___

Modified Bank # _______

New ____

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 0051AA2.02 0051AA2.02 Importance Rating 3.9 4.1 Tier # 1 1 Group # 1 1

Question 8 Given the following conditions:

Unit 2 has just tripped.

SPTA immediate operator actions have been completed.

Both 1E AC 4160 volt busses and associated Load Centers and Motor Control Centers are de-energized.

Station Blackout has been diagnosed.

Which ONE (1) of the following Motor Control Centers is used to cross-connect the 3B04 and 2B04 busses?

A. MCC 2BE B. MCC 2BY C. MCC BQ D. MCC BS Answer: C

References:

SO23- 12-8 Question Source: Bank # ___ ____

Modified Bank # ___X __

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis _ __

Examination Outline Cross-reference:

Level RO SRO K/A # 000055EA1.07 000055EA1.07 Importance Rating 4.3 4.5 Tier # 1 1 Group # 1 1

Question 9 Which ONE (1) of the following pairs of Reactor Trip Circuit Breakers would indicate open on a loss of 120V Vital AC bus Y001?

A. 1 and 5.

B. 2 and 7.

C. 3 and 6.

D. 4 and 8.

Answer: A.

References:

Question Source: Bank # ___ ____

Modified Bank # _____ __

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000057AA2.19 000057AA2.19 Importance Rating 4.0 4.3 Tier # 1 1 Group # 1 1

Question 10 Given the following conditions:

Unit 3 is operating at 100% Power

Nuclear service water pump P-138 is running in manual and Nuclear Service Water Pump P-139 is secured in AUTO.

Combined pump discharge header pressure on CR-61 is 137 psig

Nuclear Service Water Pump P-138 trips on overcurrent.

Assuming no further operator action, which ONE (1) of the following indications as monitored in the control room would indicate that P-139 has started and is operating properly?

A. Nuclear service water pressure low annunciator window on CR-61 goes out and combined pump discharge header pressure on CR-61 returns to 137 psig.

B. Nuclear service water pressure low annunciator window on CR-61 starts to slow flash and combined pump discharge header pressure on CR-61 returns to 87 psig.

C. Nuclear service water pressure low annunciator window on CR-61 goes out and combined pump discharge header pressure on CR-61 returns to 87 psig.

D. Nuclear service water pressure low annunciator window on CR-61 starts to slow flash and combined pump discharge header pressure on CR-61 returns to 137 psig.

Answer: B

References:

SO23-450 Question Source: Bank # ___ ___

Modified Bank # _______

New ___X___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000062AA1.02 000062AA1.02 Importance Rating 3.2 3.3 Tier # 1 1 Group # 1 1

Question 11 Given the following conditions:

A fire has occurred in the Unit 2 30' Turbine Building switchgear room.

The Ops Fire Technical Advisor informs the Shift Manager in the Control Room that the Fire Department Incident Commander intends to use water to extinguish the fire.

Some of the switchgear in the area is still energized.

Which ONE (1) of the following describes the action required?

A. Prohibit the use of water as an extinguishing agent in the vicinity of all electrical components, whether energized or deenergized.

B. Inform the Incident Commander an alternate fire suppression agent must be used if any energized switchgear is actively involved in the fire.

C. Permit the use of water as a fire suppression agent only after all switchgear in the area has been completely deenergized.

D. Ensure the Incident Commander is aware of the energized switchgear, and let the Incident Commander determine the most appropriate extinguishing agent.

Answer: D

Reference:

Question Source: Bank # ___X___

Modified Bank # _______

New _______

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000067AA1.08 000067AA1.08 Importance Rating 3.4 3.7 Tier # 1 1 Group # 1 1

Question 12 Given the following conditions:

The following annunciators are received in the Control Room

Alarm 61A15 "FIRE",

Alarm 61A11 "FIRE PUMP P-220(E) RUNNING"

Alarm 61A12 "FIRE PUMP P-221(C) RUNNING"

Alarm 61A13 "FIRE PUMP P-222(W) RUNNING" A report is received from the plant that there is heavy black smoke in area 2-AC-30-26 (Train B Control Room Emergency HVAC fan room).

In accordance with AOI SO23-13-2, Shutdown from Outside the Control Room, which ONE (1) of the following describes the correct method of shutting down the reactor?

A. Open the output breakers for the CEDM motor-generator units B. Secure the RCPs from control handswitches or by selecting the 6.9KV buses to manual and opening all feeder breakers C. Trip the reactor from either set of manual trip pushbuttons D. Open the input breakers for the CEDM motor-generator units Answer: C

References:

SO23-13-2 Question Source: Bank # __ ____

Modified Bank # _______

New __X .

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000068AK2.02 000068AK2.02 Importance Rating 3.7 3.9 Tier # 1 1 Group # 1 1

Question 13 Given the following plant conditions:

The reactor is tripped on Steam Generator low level due to a feed line break inside containment.

186 Lockout relay is dropped on normal supply breaker for bus 2A04.

SIAS/CIAS were manually initiated.

Which ONE (1) of the following statements is correct concerning the remaining design capacity for reducing temperature and pressure in containment, and design capacity for Iodine removal?

A. Temperature and pressure reducing capability 50%, Iodine removal capability 50%

B. Temperature and pressure reducing capability 100%, Iodine removal capability 100%

C. Temperature and pressure reducing capability 150%, Iodine removal capability 200%

D. Temperature and pressure reducing capability 100%, Iodine removal capability 50%

Answer: B

Reference:

SO23-740 Question Source: Bank # __ ____

Modified Bank # _______

New __X .

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000069EK1.2 000069EK1.2 Importance Rating 3.3 3.6 Tier # 1 1 Group # 1 1

Question 14 Given the following conditions:

The plant tripped due to a Loss of Offsite Power 15 minutes ago.

A bus lockout occurred on Electrical Bus 2A04 and cannot be reset.

AFW Pump P-140 trips on over speed and cannot be reset.

Due to a circuit malfunction EFAS failed to actuate.

SO23-12-6, Loss of Feed Water, has been entered.

RCS pressure is 2100 psia and rising.

Both Steam Generator levels are 35% WR and dropping.

Which ONE (1) of the following describes the action required to restore Feedwater flow?

A. Establish Low Pressure Alternate Feedwater flow to the S/Gs using Condensate pumps.

B. Re-establish Main Feedwater flow to the S/Gs.

C. Establish Feedwater flow to the S/Gs using P-141and P-504.

D. Establish Feedwater flow to the S/Gs using P-504.

Answer: D.

References:

SO23-12-6 Question Source: Bank # __ ____

Modified Bank # _______

New _ _X __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000074EK3.11 000074EK3.11 Importance Rating 4.0 4.1 Tier # 1 1 Group # 1 1

Question 15 Given the following conditions:

A LOCA has been identified

Pressurizer pressure is 1250 psia and steady

Pressurizer level is 100% and steady

HPSI injection valves are fully open

Thot is 552ºF

Tcold is 545ºF

REP CET is 562ºF

No RCPs are running

Containment temperature is 195°F

Containment pressure is 11 psig

A cooldown is in progress using steam generators Which ONE (1) of the following actions will be performed by the crew?

A. Secure HPSI pumps to allow RCS to depressurize so maximum injection flow with the LPSI system can be achieved.

B. Throttle HPSI flow to allow depressurization of the primary system and prevent pressurized thermal shock.

C. Throttle HPSI flow to restore pressurizer level to indicating range.

D. Continue maximum HPSI injection flow to ensure adequate cooling for the core.

Answer: D Handout reference material: Steam Tables Question Source: Bank # ___ ___

Modified Bank # ______

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis _X_

Examination Outline Cross-reference:

Level RO SRO K/A # E03EK2.1 E03EK2.1 Importance Rating 3.6 4.0 Tier # 1 1 Group # 1 1

Question 16 Given the following conditions:

Unit 2 has high RCS Activity and is in the process of cooling down on SDC.

The SDC Purification System is in service.

It has become necessary to replace the CVCS Purification Filter, 2F-020, cartridge.

Which ONE (1) of the following describes the sources used to fill and vent 2F-020 following filter cartridge replacement?

A. Nuclear Service Water and returned to the VCT.

B. Primary Plant Make Up Water and returned to Radwaste.

C. Primary Plant Make Up Water and returned to the VCT.

D. Nuclear Service Water and returned to Radwaste Answer: D

References:

Question Source: Bank # ___X ___

Modified Bank # ____ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X __

Comprehension or Analysis ___ _

Examination Outline Cross-reference:

Level RO SRO K/A # 000076G2.1.32 000076G2.1.32 Importance Rating 3.4 3.8 Tier # 1 1 Group # 1 1

Question 17 Given the following conditions:

CEA Group 5 is being withdrawn from 108 inches to 123 inches.

At 112 inches on Group 5 the operator releases the CEDMCS joystick.

CEA 14 and 15 motion STOPS.

CEA 16 and 17 CONTINUE to withdraw.

The CO terminates all CEA motion by placing CEDMCS in OFF.

CEA 16 and 17 indicate 123 inches.

Which ONE (1) of the following actions is required, and what is the reason for the action?

A. Restore Group 5 alignment within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by inserting CEA 16 and 17 using MANUAL INDIVIDUAL to preclude excessive power peaking.

B. Immediately open all RTCB's to preclude operation outside of design basis.

C. Reduce thermal power to limits specified in the COLR within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to preclude operation outside of DNBR limits.

D. Restore Group 5 alignment within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by withdrawing CEAs 14 and 15 in MANUAL INDIVIDUAL to prevent exceeding AZTILT limits Answer: B

References:

Question Source: Bank # ___ ___

Modified Bank # ___X__

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __ X_

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000001G2.2.25 000001G2.2.25 Importance Rating 2.5 3.7 Tier # 1 1 Group # 2 2

Question 18 Given the following conditions:

Unit 2 is at 85% power

Group 6 is at 149 inches withdrawn

Recovery of a Dropped CEA (#20) is in progress

CEA # 20 is at 100 inches withdrawn The following indications occur:

Pressurizer level begins to drop

Pressurizer pressure is dropping slowly

Thot, Tcold, and Tave are dropping

Reactor power is 80% and dropping Which ONE (1) of the following is the cause of these conditions?

A. An ADV on a steam generator has started leaking B. There is a small break loss of coolant accident in progress C. Another CEA has dropped D. These are expected indications during recovery of the dropped CEA.

Answer: C

References:

Question Source: Bank # ___ ___

Modified Bank # _______

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis ___X_

Examination Outline Cross-reference:

Level RO SRO K/A # 000003AA1.06 000003AA1.06 Importance Rating 4.0 4.1 Tier # 1 1 Group # 2 2

Question 19 Given the following plant conditions:

A small break Loss of Coolant Accident has occurred.

RCPs have been secured

HPSI Pumps P-018 and P-019 have been secured

All Three (3) charging pumps are running

Pressurizer pressure is 1095 psia and steady

Pressurizer level is 100%

S/G Levels are E088 62% NR and E089 60% NR

Thot is 550º F

Tcold is 540º F

Core exit thermocouple temperature is 555º F Which ONE (1) of the following actions is required for these conditions?

A. Secure two (2) Charging Pumps and energize PZR heaters to restore RCS Pressure and reduce Pzr level.

B. Commence bleeding steam from the steam generators to establish natural circulation flow.

C. Secure two (2) Charging Pumps and de energize PZR heaters to prevent over pressurizing the RCS.

D. Restart RCPs to commence RCS cooldown and lower pressurizer level Answer: B References for student: Steam Tables

References:

SO23-12-3 Question Source: Bank # ___ ___

Modified Bank # _______

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis ___X_

Examination Outline Cross-reference:

Level RO SRO K/A # 000007EK1.06 000007EK1.06 Importance Rating 3.4 3.9 Tier # 1 1 Group # 2 2

Question 20 Given the following plant conditions:

Safety Injection Actuated

PZR Pressure is 1700 psig and slowly LOWERING

RCS Temperature is 545º F and slowly LOWERING

S/G NR Levels are 1% and slowly RISING

Quench Tank Pressure is 21 psig and STABLE

S/G Pressures are 1000 psig and STABLE

PZR Level is 28% and RISING

Containment Temperature is 140°F and slowly RISING

Containment Pressure is 2 psig and RISING

Containment Humidity is RISING Which ONE (1) of the following is the cause of the above conditions?

A. RCS leak from a cold leg.

B. S/G Safety Valve failed open.

C. RCS Safety Valve failed open.

D. Pressurizer steam space leak.

Answer: D Question Source: Bank # ___X___

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis ___X_

Examination Outline Cross-reference:

Level RO SRO K/A # 000008AK2.02 000008AK2.02 Importance Rating 2.7 2.7 Tier # 1 1 Group # 2 2

Question 21 Given the following conditions:

A Unit 2 shutdown is in progress from 100% power.

During the shutdown, a reactor trip occurred due to a loss of coolant accident concurrent with a loss of offsite power.

The following plant conditions exist:

Emergency Diesel Generators are operating normally

RCS Th 555º F

Pressurizer Pressure 1200 psia

Pressurizer Level 34% and stable

Reactor Vessel Head Level indicates 2 voids

Steam Generator E089 NR level 25% with auxiliary feedwater flow established

Steam Generator E088 NR Level 26% with auxiliary feedwater flow established

Containment Temperature 148º F

Core Exit Temperatures are 560º F Which ONE (1) of the following parameters will NOT allow performance of HPSI Throttle/Stop?

A. Subcooling Margin.

B. Reactor Vessel Head Level.

C. Pressurizer Level.

D. Steam Generator Steam / Feed Flow.

Answer: A Question Source: Bank # __X___

Modified Bank # _______

New .

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 00009EA3.26 00009EA3.26 Importance Rating 4.4 4.5 Tier # 1 1 Group # 2 1

Question 22 Given the following conditions:

A reactor trip has occurred.

Immediate actions of SO23-12-1, "Standard Post Trip Actions," have been completed.

The crew is attempting to diagnose the accident.

Plant conditions are as follows:

Group 6 CEA #28 indicates fully withdrawn

E088 and E089 levels are 24% narrow range and rising slowly

E088 and E089 pressures are 1000 psia and stable

Pressurizer level is 28% and lowering

Pressurizer pressure is lowering rapidly

Containment pressure is 0 psig

Containment area radiation monitors and Main Steam Line radiation monitors are normal Which ONE (1) of the following events is in progress?

A. PZR Spray valve stuck open.

B. LOCA outside Containment.

C. LOCA inside Containment.

D. Steam Line Break outside Containment.

Answer: B

References:

SO23-12-1 Question Source: Bank # ___ ___

Modified Bank # ___X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # E04EA2.01 E04EA2.01 Importance Rating 3.6 4.2 Tier # 1 1 Group # 2 2

Question 23 Given the following conditions:

Unit 2 has experienced a Reactor trip from 100% power due to a fault in the turbine control system.

S/G Levels indicate:

o E088 - 65% NR o E089 - 68% NR

Pzr level is 30% and slowly lowering

Pzr pressure is 2240 psia

Letdown is secured

SBCS is operating to maintain S/G pressures at 1000 psia

Quench Tank Press HI, (50A01) has come in and cleared

Quench Tank Level HI/LO, (50A11) is locked in

Quench Tank Temp HI, (50A21) is locked in

PZR Safety Valve outlet Temp HI, (50A31) is locked in

Containment pressure is 1.8 psia and rising.

Containment temperature and humidity are rising Which ONE (1) of the following describes the mitigation strategy for the event in progress?

A. Initiate a manual Safety Injection to provide makeup water to the RCS.

B. Commence RCS cooldown using the S/Gs and the SBCS.

C. Commence RCS cooldown at maximum achievable rate using ADVs.

D. Open PZR normal and auxiliary spray valves to rapidly reduce pressure to less than 1400 psia.

Answer: B

References:

SO23-15-50.A1 SOSO23-360 SO23-14-3 SO23-12-11 Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # E03EK3.3 E03EK3.3 Importance Rating 3.9 3.9 Tier # 1 1 Group # 2 2

Question 24 Given the following conditions:

A Large Break LOCA has occurred

HPSI and LPSI pumps are injecting

A Recirculation Actuation Signal (RAS) actuates.

Which ONE (1) of the following describes the impact on the long term core cooling if the Safety Injection Pump minimum recirculation flow valves (HV-9306, 9307, 9347, and 9348) FAIL to shut?

A. No impact, system is designed with minimum flow valves to protect the pumps from overheating in a low flow condition.

B. Cooling flow through the core will be reduced by a small amount, but no other impact.

C. Cooling flow through the core will be reduced then lost as coolant inventory is lost from the containment emergency sump.

D. The parallel flow path will result in higher total flow from the pumps with no reduction in flow through the core.

Answer: C

Reference:

SO23-740 Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # W/E11EK2.2 W/E11EK2.2 Importance Rating 3.9 4.3 Tier # 1 1 Group # 2 2

Question 25 Given the following conditions:

Pressurizer pressure is 1250 psia.

Pressurizer level is 100%.

HPSI injection is 330 gpm/cold leg.

Thot is 550º F.

Tcold is 510º F.

Core exit thermocouple temperature is 560º F.

Reactor vessel level monitoring system indicates 100% in plenum and TWO (2) voids in the head.

All RCPs are TRIPPED.

Containment temperature is 195º F.

Containment pressure is 11 psig.

SIAS, CIAS, and MSIS have actuated.

A cooldown is in progress using steam generators.

Which ONE (1) of the following identifies the action required in regard to HPSI flow?

A. Continue maximum injection flow until subcooling is at least 20 degrees F.

B. HPSI flow may be throttled to restore pressurizer level in control band.

C. HPSI flow may be throttled to allow depressurization of the primary system.

D. Continue maximum injection flow until the reactor vessel level monitoring system indicates no voids in the head.

Answer: A

References:

Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis __X_

Examination Outline Cross-reference:

Level RO SRO K/A # E01/E02EK1.1 E01/E02EK1.1 Importance Rating 3.9 4.3 Tier # 1 1 Group # 2 2

Question 26 Given the following conditions:

A LOCA has occurred on Unit 2.

All ECCS equipment is functioning as designed.

RCS pressure is 1000 psia and STABLE

Highest Core Exit Thermocouple temperature is 455º F and TRENDING DOWN slowly

Containment Pressure is 9 psig and rising.

Containment Temperature is 168º F and TRENDING up slowly

The crew is performing the actions of SO23-12-3, Loss of Coolant Accident

The CO trips ALL RCPs.

Which ONE (1) of the following describes the basis for tripping all RCPs at this time?

A. RCPs are required to be stopped when a loss of subcooling is indicated.

B. RCPs must be stopped to prevent additional RCS inventory loss.

C. RCPs must be stopped to prevent damage due to loss of cooling water.

D. RCPs must be stopped because there is insufficient NPSH to prevent cavitation of the pumps.

Answer: C

Reference:

Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ _

Examination Outline Cross-reference:

Level RO SRO K/A # 000022AK3.06 000022AK3.06 Importance Rating 3.2 3.3 Tier # 1 1 Group # 2 2

Question 27 Given the following conditions:

Unit 2 is shutdown

Cooldown is in progress at 40º F/hr.

RCS Temperature is 280º F

RCS pressure is 300 psia,

Train B CCW Surge Tank Level has risen from 40% to 55% in 20 minutes.

Pressurizer Level is 60% and stable.

VCT level dropped from 77% to 73% in 20 minutes.

Which ONE (1) of the following components is causing the CCW Surge Tank Level rise?

A. Spent Fuel Pool heat exchanger tube leak.

B. Shutdown Cooling heat exchanger tube leak C. CEDMCS Cooler leak.

D. Steam Generator sample cooler leak Answer: B

Reference:

Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ _

Examination Outline Cross-reference:

Level RO SRO K/A # 000025AA2.02 000025AA2.02 Importance Rating 3.4 3.8 Tier # 1 1 Group # 2 2

Question 28 WHICH ONE (1) of the following describes how the ATWS Diverse Scram System trips the reactor?

A. Outputs from logic channels 1 and 3 or 2 and 4 are required to open both M-G set contactors to trip the reactor.

B. Outputs from logic channels 1 and 2 or 3 and 4 are required to activate the undervoltage relay to trip the M-G set contactors to trip the reactor C. Outputs from logic channels 1 or 3 and 2 or 4 are required to open both M-G set contactors to trip the reactor.

D. Outputs from logic channels 1 or 3 and 2 or 4 are required to activate the undervoltage relay to trip the M-G set contactors to trip the reactor.

Answer: C

Reference:

SO23-520 Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ _

Examination Outline Cross-reference:

Level RO SRO K/A # 000029EA1.08 000029EA1.08 Importance Rating 4.5 4.5 Tier # 1 1 Group # 2 2

Question 29 Which ONE (1) of the following describes the effect on the Excore Nuclear Instrumentation (NI)

Log Safety Channel response if the voltage applied to the fission chamber is too HIGH?

A. The Excore NIs shift from a count rate circuit to a Campbelling circuit at a lower indicated power level.

B. The Excore NIs shift from a Campbelling circuit to a count rate circuit at a higher actual nuclear power.

C. The Excore NIs shift from a count rate circuit to a Campbelling circuit at a lower actual nuclear power level.

D. The Excore NIs shift from a Campbelling circuit to a count rate circuit at a higher indicated nuclear power.

Answer: C

Reference:

SO23-470 Question Source: Bank # ___ ___

Modified Bank # _______

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000032AK1.01 000032AK1.01 Importance Rating 2.5 3.1 Tier # 1 1 Group # 2 2

Question 30 The following conditions exist:

The reactor has tripped

CEA's 23 and 24 are NOT inserted

Boration is in progress at 41gpm

Reactor power 1X10-2% and dropping

SUR is negative

Standard Post Trip Actions (SPTA) are in progress The Reactivity Control Safety Function acceptance criteria:

A. will NOT be satisfied until the boration is increased to >44 gpm.

B. is currently satisfied; boration should continue until adequate shutdown margin is established.

C. is currently satisfied; boration may be terminated.

D. will NOT be satisfied until at least one (1) of the stuck CEA's is inserted.

Answer: B

Reference:

Question Source: Bank # ___ ___

Modified Bank # __X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000033AA2.07 000033AA2.071 Importance Rating 3.9 4.2 Tier # 1 1 Group # 2 2

Question 31 Given the following conditions:

Unit 2 has been operating at 97% power for the last 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months after completing maintenance on the MFW pump.

Turbine load is 1176 MW and steady

Pzr level is 48% and lowering slowly

Pressurizer pressure is 2220 psia and lowering slowly

Thot is 598ºF

Tcold is 538ºF

Tave is 563ºF

Steam Generator E088 parameters are:

o Pressure: 805psig o FW Flow: 15,000 gpm o Stm Flow: 7.7 x 10 6th lbm/hr

Steam Generator E089 parameters are:

o Pressure: 805psig o FW Flow: 15,360 gpm o Stm Flow: 7.5 x 10 6th lbm/hr

Feedwater Temperature is 445ºF

Containment pressure is 0 psig, temperature and humidity are stable.

Which ONE (1) of the following events is taking place?

A. A steam generator tube rupture is in progress on SG E088 B. The plant is responding to Xenon buildup following the up power.

C. There is a steam leak on steam generator SG E088 D. The plant is responding to Xenon burnout following the up power.

Answer: A

References:

Question Source: Bank # ___ ___

Modified Bank # _______

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000038EA1.01 000038EA1.01 Importance Rating 3.5 3.9 Tier # 1 1 Group # 2 2

Question 32 Given the following conditions:

The plant had been operating at full power conditions for three months.

The CRS has completed the Standard Post Trip Actions and entered the Station Blackout procedure.

MSIS has been initiated.

Auxiliary Feedwater pump P-140 started

AC power has NOT been restored.

Steaming is being controlled by the ADVs

E088 level is 22% NR and lowering

E089 level is 21% NR and lowering

Thot is 556º F and steady

Tcold is 495º F and steady

Core exit thermocouple temp is 585º F Which ONE (1) of the following describes the condition of the RCS and the action required in accordance with SO23-12-8, Station Blackout?

A. Single flow natural circulation has been established; minimize steaming on the ADVs to maintain RCS in hot standby. Use the AFW pump to feed S/Gs to maximum allowable level but less than 80% NR until main feedwater can be restored.

B. Single flow natural circulation has NOT been established, secure steaming on the ADVs to maintain S/G inventory until normal source of feedwater can be restored C. Single flow natural circulation has NOT been established. Raise at least one S/G level to maximum allowable level but less than 80% NR or feedwater flow rate of at least 200 GPM and increase the steaming rate on the ADVs D. Two-phase flow natural circulation has been established. Maintain the AFW system in automatic to control S/G levels, increase the steaming rate on the ADVs Answer: C

References:

SO23-12-8 SO23-14-8 Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __ _ _

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # E04G2.4.14 E04G2.4.14 Importance Rating 3.0 3.9 Tier # 1 1 Group # 2 2

Question 33 Which ONE (1) of the following describes the effect of a loss of DC Bus 2D3 on the operation of Auxiliary Feed Water Pump P-140?

A. All P-140 discharge valves to both Steam generators will fail open.

B. All P-140 discharge valves to both Steam generators will fail closed.

C. P-140 will not automatically start.

D. P-140 will go to 3600 rpm if running.

Answer: C.

References:

SO23-140 125 and 250 VDC system SO23-6-15 SO-23-12-6 SO23-2-4 Question Source: Bank # ___X___

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000058AA2.03 000058AA2.03 Importance Rating 3.5 3.9 Tier # 1 1 Group # 2 2

Question 34 Given the following conditions:

Unit 3 was at 100% power.

A complete loss of off-site power occurred 15 minutes ago.

Buses have been re energized from the emergency diesel generators.

There are no RCPs running

Letdown flow has been restored

Pzr Level is 68% and slowly lowering

PZR Pressure is 2320 psia and slowly lowering

MSIVs are closed In accordance with SO23-12-7, Loss of Forced Circulation/Loss of Off-Site Power, which ONE (1) of the following actions is required?

A. Operate the AFW system to establish 200 gpm flow rate to each S/G for at least 5 minutes.

B. Operate AFW system to establish at least one intact S/G level between 40% and 80% on the narrow range indication.

C. Operate MFW system to establish at least one intact S/G level between 40% and 80% on the narrow range indication.

D. Operate the MFW system and use main steam Safety valves to steam the S/Gs to establish natural circulation and decay heat removal.

Answer: B Reference SO 23-12-7 step 9 Question Source: Bank # ___ ___

Modified Bank # ___ __

New __ X _

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 000056A3.02 000056A3.02 Importance Rating 4.4 4.7 Tier # 1 1 Group # 3 3

Question 35 Given the following plant conditions:

Unit 2 is tripped following a Steam Generator Tube Rupture.

RCS pressure is 970 psia.

Thot is 490ºF

SG E089 pressure is 890 psia.

SG E089 is isolated.

SG E089 level is 82% NR and rising slowly.

SG E088 level is 50% NR and steady.

Which ONE (1) of the following is the preferred method to control level in the isolated steam generator?

A. Bypass the MSIV and steam E089 Steam Generator to the condenser.

B. Lower RCS pressure below E089 Steam Generator pressure and allow backflow to the RCS.

C. Steam E089 Steam Generator to atmosphere via the ADVs.

D. Lineup high rate blowdown to the condenser from E089 Steam Generator.

Answer: B

Reference:

Question Source: Bank # __X___

Modified Bank # ___ __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X __

Comprehension or Analysis __ ___

Examination Outline Cross-reference:

Level RO SRO K/A # W/E13G2.3.11 W/E13G2.3.11 Importance Rating 2.7 3.2 Tier # 2 2 Group # 1 1

Question 36 Given the following conditions:

A Large Break LOCA has occurred

All ECCS pumps are operating as required.

A Recirculation Actuation Signal (RAS) actuates.

Which ONE (1) of the following describes the resulting ECCS alignment?

A. LPSI pumps stopped, HPSI pumps recirculating RCS to the RWST.

B. LPSI pumps recirculating the RCS, HPSI pumps injecting from RWST.

C. HPSI pumps stopped, LPSI pumps recirculating the RCS to the containment sump.

D. LPSI pumps stopped, HPSI pumps recirculating the RCS to the containment sump.

Answer: D

Reference:

Question Source: Bank # __X___

Modified Bank # ___ __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X __

Comprehension or Analysis __ ___

Examination Outline Cross-reference:

Level RO SRO K/A # W/E15EA1.3 W/E15EA1.3 Importance Rating 2.8 3.0 Tier # 1 1 Group # 3 3

Question 37 Given the following conditions:

The plant has just experienced a trip due to grid instabilities

Charging pump 2P191 has been tagged out for maintenance.

Charging pump 2P190 is running and Charging Pump 2P192 is in standby

CEA 23 is stuck fully withdrawn,

CEA 24 is stuck at 110 steps withdrawn

Power has been lost to 480 Volt Load center 2B06

Charging pump 2P190 trips on loss of suction pressure In accordance with SO23-13-11 Emergency Boration of Reactor Coolant System / Inadvertent Dilution or Boration, which ONE (1) of the following operator actions is required under these conditions?

A. Borate via gravity feed suction path B. Lower RCS pressure and borate via HPSI C. Initiate RCS cooldown and initiate SIAS to borate the reactor D. Stabilize RCS temperature and pressure until at least one charging pump can be restored to operation, then borate.

Answer: B.

References:

SO23-13-11 Emergency Boration of Reactor Coolant System / Inadvertent Dilution or Boration Question Source: Bank # ___ ___

Modified Bank # ___X__

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 001A2.03 001A2.03 Importance Rating 3.5 4.2 Tier # 2 2 Group # 1 1

Question 38 Given the following conditions:

Reactor startup is in progress.

Critical data has just been recorded.

A 20-second continuous rod withdrawal event now occurs due to the CEDMCS joystick being inadvertently stuck in RAISE.

The CO is able to unstick the joystick and return it to neutral.

Assuming no other action is taken by the crew, which ONE (1) of the following parameters will stabilize at a value GREATLY different from what it was before the event?

A. Pressurizer level B. Steam generator pressures C. Nuclear instrumentation power D. RCS Hot and Cold leg Temperatures Answer: C

References:

Question Source: Bank # ___ ___

Modified Bank # ___ ___

New ___X .

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 001A3.06 001A3.06 Importance Rating 3.9 3.9 Tier # 2 2 Group # 1 1

Question 39 Given the following conditions:

Reactor is shutdown following a Station blackout.

All RCPs are TRIPPED

Electrical Power has been restored and preparations are under way to restore forced circulation in the Reactor.

Tave is 530ºF

Tcold is 525ºF

Thot is 535ºF

Pressurizer level is 45%

Pressurizer pressure is 2200psia

Steam Generator level is:

o E088 51% NR o E089 48% NR

Steam Generator pressures are 1000 psia being controlled by ADVs.

In accordance with the appropriate operating procedures and instructions, which ONE (1) of the following actions must be taken before starting reactor coolant pumps?

A. Reduce steam generator pressures to less than 920 psia.

B. Energize Pressurizer heaters to raise RCS Pressure to greater than 2235 psia.

C. Start a charging pump and raise pressurizer level to greater than 53%.

D. Place both lift oil pumps in normal until at least one Reactor Coolant Pump is running in each loop and RCS temperatures have stabilized.

Answer: A Student Reference Material required:

Attachments 4 and 5 of OPERATING INSTRUCTION SO23-3-1.7 Steam Tables

Reference:

OPERATING INSTRUCTION SO23-3-1.7 Question Source: Bank # ___ ___

Modified Bank # _______

New ___X .

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 003K6.14 003K6.14 Importance Rating 2.6 2.9 Tier # 2 2 Group # 1 1

Question 40 Given the following conditions:

Unit 3 is at 99% power

RCP P-001 seal cavity pressures are approximately equal to reactor coolant system pressure.

A calculation of the RCS leak rate has just been completed and is the same as the previously calculated rate.

All radiation levels are normal Which ONE (1) of the following describes the cause of the above indications?

A. Inadvertent closure of RCP P-001 controlled bleed off excess flow check valve.

B. Failure of the vapor seal.

C. Excessive Controlled Bleed-Off flow.

D. Failure of RCP P-001 middle seal.

Answer A Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 003K1.03 003K1.03 Importance Rating 3.3 3.6 Tier # 2 2 Group # 1 1

Question 41 Given the following conditions:

Unit 3 is at 100% power

Pressurizer level is at 43% and lowering

Tcold is 539ºF

Power is lost to 480V Bus 3B04

P-191 is aligned to Train B Which ONE (1) of the following describes the operation of the CVCS for these conditions?

A. Charging pumps P-190, P-191, and P-192 running with letdown flow at minimum.

B. Charging pumps P-190 and P-191running with letdown flow at maximum.

C. Charging pumps P-191 and P-192 running with letdown flow at minimum.

D. Charging pumps P-191 and P-192 running with letdown flow at maximum.

Answer: C Question Source: Bank # ___ ___

Modified Bank # _______

New ___X .

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 004K2.03 004K2.03 Importance Rating 3.3 3.5 Tier # 2 2 Group # 1 1

Question 42 Given the following conditions:

Unit 2 is operating at 100% power

Volume Control Tank (VCT) Level Transmitter 2LT-227 fails LOW.

Which ONE (1) of the following describes the effect of this failure on the Chemical and Volume Control System (CVCS)?

A. A continuous automatic makeup demand signal would be present; high and low level alarms are disabled.

B. Automatic diversion of the VCT inlet valve on high level is disabled; high and low level alarms are disabled.

C. Automatic diversion of the VCT inlet valve on high level is disabled; Charging pump suction automatically aligns to the RWST.

D. A continuous automatic makeup demand signal would be present; Charging pump suction automatically aligns to the Boric Acid Makeup Tanks.

Answer: C

Reference:

Question Source: Bank # ___ __

Modified Bank # _______

New ___X .

Question Cognitive Level: Memory or Fundamental Knowledge _ __

Comprehension or Analysis __ X__

Examination Outline Cross-reference:

Level RO SRO K/A # 004K1.04 004K1.04 Importance Rating 3.4 3.8 Tier # 2 2 Group # 1 1

Question 43 Given the following conditions:

E088 S/G Pressure is 725 psia

E089 S/G pressure is 1000 psia

Pressurizer pressure is 1600 psia

Pressurizer Level is 42%

Containment pressure is 12 psig

Containment Hi Range radiation monitor reads 13 R/hr and is rising Which ONE (1) of the following ESFAS actuations has NOT automatically initiated?

A. CRIS B. SIAS C. MSIS D. CSAS Answer: D Question Source: Bank # __X____

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 013A1.03 013A1.03 Importance Rating 2.6 2.6 Tier # 2 2 Group # 1 1

Question 44 Given the following conditions:

An EFAS actuation has occurred.

S/G-E089 Level = 15% NR

S/G-E089 Pressure = 580 psia

S/G-E088 Level = 20% NR

S/G-E088 Pressure = 710 psia Which ONE (1) of the following describes the automatic operation of the EFAS System?

A. AFW is feeding BOTH S/Gs.

B. AFW is isolated to BOTH S/Gs.

C. AFW is feeding S/G-E089 ONLY.

D. AFW is feeding S/G-E088 ONLY.

Answer: D Question Source: Bank # ___X___

Modified Bank # .

New _______

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 013A3.02 013A3.02 Importance Rating 4.1 4.2 Tier # 2 2 Group # 1 1

Question 45 Given the following conditions:

Unit 3 is operating at 85% power.

Surveillance testing is in progress on the Excore Nuclear Instruments

The following channel trips are received:

o High LPD and Low DNBR Which ONE (1) of the following Excore Nuclear Instrumentation switch manipulations would cause this?

A. Placing the Linear Calibrate Switch to "Zero" B. Placing the Rate Calibrate Switch to "Zero" C. Placing the Log Calibrate Switch to "Zero" D. Placing the Linear Calibrate Switch to "125%"

Answer: B Question Source: Bank # _______

Modified Bank # X .

New _______

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 015K6.04 Importance Rating 3.1 Tier # 2 Group # 1

Question 46 The following plant conditions exist:

Large Break Loss of Coolant Accident has occurred.

All Reactor Coolant Pumps are STOPPED.

NO Safety Injection Flow is available.

Reactor Coolant in the core region is at saturated conditions.

Which ONE (1) of the following describes the response of the Excore Nuclear Instrumentation System Startup Channels as the coolant in the core region is initially boiled off and level in the core drops?

A. Count rate lowers because there are fewer neutrons generated.

B. Count rate rises because there are more neutrons generated C. Count rate rises because the level in the down comer drops.

D. Count rate lowers because the level in the down comer rises.

Answer: C

References:

Question Source: Bank # __ ____

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 015G2.2.2 015G2.2.2 Importance Rating 4.0 3.5 Tier # 2 2 Group # 1 1

Question 47 Given the following conditions:

A LOCA has occurred on Unit 2

Pzr Pressure is 1100 psia

Pzr level is 12% and slowly rising

Thot is 561ºF

Tcold is 557ºF Which ONE (1) of the following additionally identifies that Core uncovery is occurring and where is the indication obtained?

A. Core Exit Thermocouple (CET) temperatures rising; Obtained from CFMS page 311.

B. Core Exit Thermocouple (CET) temperatures rising; Obtained from QSPDS page 311.

C. Core Exit Thermocouple (CET) temperatures steady; Obtained from QSPDS page 411.

D. Core Exit Thermocouple (CET) temperatures steady; Obtained from CFMS page 411.

Answer: A

References:

SO23-12-8 Question Source: Bank # __ ____

Modified Bank # __ _____

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 017A4.01 017A4.01 Importance Rating 3.8 4.1 Tier # 2 2 Group # 1 1

Question 48 Given the following conditions:

Unit 2 is at 100% power.

ONE (1) Core Exit Thermocouple failed to ZERO (0) output.

Which ONE (1) of the following describes the effect of this failure on the Qualified Safety Parameter Display System (QSPDS) Representative CET (REPCET) reading?

A. Indicates lower; 0 temp indication is averaged into calculation.

B. Does not change; input not used in calculation.

C. Indicates lower; flagged as invalid.

D. Indication will flash indicating failure of input; Operator can manually delete failed input to restore display.

Answer: B

Reference:

Question Source: Bank # __ _ ___

Modified Bank # __ _X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge ___X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 017K3.01 017K3.01 Importance Rating 3.5 3.7 Tier # 2 2 Group # 1 1

Question 49 Given the following conditions:

RCS pressure, temperature, power, and inventory stable.

Steam Generator pressure and levels stable.

Containment temperature, pressure, and humidity rising rapidly.

Containment Sump rising at a rate equal to 150 gpm.

Which ONE (1) of the following events is in progress?

A. RCS leak in Containment.

B. Main Steam leak in Containment.

C. CCW leak in Containment.

D. Main Feedwater leak in Containment.

Answer: D.

References:

Question Source: Bank # __ ____

Modified Bank # __ _____

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 022A4.05 022A4.05 Importance Rating 3.8 3.8 Tier # 2 2 Group # 1 1

Question 50 Given the following plant conditions:

The reactor is tripped.

SIAS is actuated.

Pressurizer level is 10% and lowering.

CSAS is NOT initiated.

Containment pressure is rising on all channels.

Containment pressure indications as follows:

o 14.0 psig on Channel 'A' o 14.5 psig on Channel 'B' o 13.0 psig on Channel 'C o 13.0 psig on Channel 'D Which ONE (1) of the following describes the action that should be performed?

A. Manually initiate CSAS due to the CSAS setpoint being met or exceeded.

B. When Channels C or D reach 13.5 psig, manually initiate CSAS.

C. When channel C or D reach 14 psig, verify CSAS automatically initiates.

D. CSAS may be initiated now based on trend, but is NOT required.

Answer: A

Reference:

Question Source: Bank # __X____

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 022A1.02 022A1.02 Importance Rating 3.6 3.8 Tier # 2 2 Group # 1 1

Question 51 Given the following conditions:

A Loss of Feedwater has occurred on Unit 2.

E089 Steam Generator level is 0% on the narrow range level indication

E088 Steam Generator level is 38% on the wide range level indication

AFW pump P-504 has been started.

Which ONE (1) of the following describes the correct sequence of actions for the conditions given?

A. Commence feeding both SGs; maintain AFW flow < 150 gpm to each SGs (Total AFW flow 300gpm). When increases in SG level observed or continuous AFW flow to the SG has been maintained for > 5 minutes, control AFW flow as necessary.

B. Commence feeding E089 SG; maintain AFW flow < 130 gpm. When increases in SG level observed or continuous AFW flow to the E089 SG has been maintained for > 5 minutes, control AFW flow as necessary.

C. Commence feeding the E088 SG; maintain AFW flow between 130gpm and 150 gpm. When increases in SG level observed or continuous AFW flow to the E088 SG has been maintained for > 5 minutes, control AFW flow as necessary.

D. Commence feeding the SGs; maintain AFW flow between 130gpm and 150 gpm to both SGs (Total AFW flow <150gpm). When increases in SG level observed or continuous AEFW flow to the SG has been maintained for > 15 minutes, control AFW flow as necessary.

Answer: C

References:

SO23-12-6 Question Source: Bank # __X____

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 059G2.4.49 059G2.4.49 Importance Rating 4.0 4.3 Tier # 2 2 Group # 1 1

Question 52 Given the following conditions:

Unit 3 is at 100% power

Pzr Level is 53%

Pzr Pressure is 2250 psia

Steam generator levels are 65% NR

A fault causes loss of power to FV-1111 (feed regulating valve for S/G E089)

Feedwater Control System #1 receives a spurious High Level Override in Steam Generator E089 Which ONE (1) of the following correctly identifies the effects on the plant?

A. Main Feed Pump Speed will not be affected, Main Feed Reg Valve will go fully closed, and Main Feed Bypass Valve will not be affected.

B. Main Feed Pump Speed will go to 3600 rpm, Main Feed Reg Valve will remain in its current position, and Main Feed Bypass Valve will go fully closed.

C. Main Feed Pump Speed will go to 3600 rpm, Main Feed Reg Valve will go fully closed, and Main Feed Bypass Valve will close to 50%.

D. Main Feed Pump Speed will not be affected, Main Feed Reg Valve will remain in its current position and Main Feed Bypass Valve will go fully closed.

Answer: D

References:

SO23-250 Question Source: Bank # _ .

Modified Bank # ___X___

New ___ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 059A2.12 059A2.12 Importance Rating 3.1 3.4 Tier # 2 2 Group # 1 1

Question 53 Given the following conditions:

A plant heatup is in progress.

Steam generator pressure is 400 psia.

A large steam leak occurs in the turbine building.

The MSIVs do NOT close.

Both steam generators start to blow down uniformly.

Which ONE (1) of the following describes the expected response of the AFW system to these events?

A. All AFW pumps will start when either steam generator level decreases to 21% NR.

B. The AFW system will not respond to these events.

C. Only the motor driven AFW pumps will start when either steam generator level decreases to 32% WR.

D. The turbine driven AFW pump will start when either steam generator level decreases to 21% NR.

Answer: D

Reference:

SO23-780 Question Source: Bank # _ .

Modified Bank # ___X___

New ___ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 061K4.06 061K4.06 Importance Rating 4.0 4.2 Tier # 2 2 Group # 1 1

Question 54 Given the following conditions:

Unit 2 tripped from 100% power 20 minutes ago.

P-140 tripped on overspeed and CANNOT be reset.

Both S/G levels lowered to 17% NR and recovered to 27%NR.

The ACO has depressed the override pushbuttons for the AFW valves and is feeding each S/G at 450 gpm.

Subsequently:

4KV bus 2A04 is de-energized due to an overcurrent condition

S/G E088 pressure decreases to 700psia with level at 25% NR

S/G E089 pressure decreases to 850psia with level at 27% NR Which ONE (1) of the following describes the status of the AFW system? (Assume no other operator actions have occurred)

A. Both S/Gs E088 and E089 are being fed B. S/G E088 is being fed and S/G E089 is not being fed C. Both S/Gs E088 and E089 are isolated D. S/G E089 is being fed and S/G E088 is not being fed Answer: B

Reference:

SO23-780 Auxiliary Feedwater System Question Source: Bank # _ .

Modified Bank # ___ ___

New ___X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X _

Examination Outline Cross-reference:

Level RO SRO K/A # 061K2.02 061K2.02 Importance Rating 3.7 3.7 Tier # 2 2 Group # 1 1

Question 55.

The liquid radwaste system is designed to provide controlled collection, handling, treatment, and disposal of radioactive wastes from plant operation.

Which ONE (1) of the following describes the principle design criteria of this system?

A. Allow processing the various potentially radioactive liquid wastes for long term storage on site.

B. Limit releases due to anticipated operational occurrences to annual liquid activity release quantity (five Ci).

C. Provide the removal of radioactivity as soon as feasible in the process, thus preventing the buildup of excessive activity in the remainder of the systems.

D. Ensure protection of general public from exposure by keeping release levels as low as possible.

Answer: D.

References:

STM-2-52 Section 1.4 Lesson Plan ASLP-RO-RADP Question Source: Bank # _ X .

Modified Bank # _______

New ___ __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 068K5.04 068K5.04 Importance Rating 3.2 3.5 Tier # 2 2 Group # 1 1

Question 56 Given the following conditions:

Gaseous radwaste lined up for receiving gas from surge header.

Oxygen content in the Volume Control Tank is 1.0% and rising.

Oxygen content in the surge header is 1.0% and rising.

Which ONE (1) of the following describes the action(s) which automatically occur(s) as oxygen content continues to rise?

A. All input into the gaseous radwaste header isolates.

B. A HIGH O2 level alarm will be received in the Control Room.

C. Volume Control Tank to gaseous radwaste header isolates.

D. Automatic nitrogen dilution of gaseous radwaste surge header prior to exceeding Technical Specification limits on oxygen.

Answer: B

Reference:

Question Source: Bank # __X ___

Modified Bank # _______

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 071K5.04 071K5.04 Importance Rating 2.5 3.1 Tier # 2 2 Group # 1 1

Question 57 Given the following conditions:

A planned release of waste gas decay tank T086 is in progress.

A high spike occurs on WRGM 2 RI-7865

The spike causes a HIGH alarm, which subsequently clears.

Which ONE (1) of the following describes the automatic action due to the high spike on the radiation monitor?

A. Stops all waste gas compressors.

B. Closes 2/3HV-7202, waste gas discharge isolation valve.

C. Starts all auxiliary building supply and exhaust fans.

D. Initiates Control Room Isolation System Actuation.

Answer: B

Reference:

Question Source: Bank # __X ___

Modified Bank # _______

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 071K3.04 071K3.04 Importance Rating 2.7 2.9 Tier # 2 2 Group # 1 1

Question 58 Given the following conditions:

Unit 3 is in MODE 6.

Irradiated Fuel movement is in progress.

A spent fuel assembly is damaged while being transported to the spent fuel racks.

Fuel Pool area radiation monitor: High Trip exceeded

Fuel Building air exhaust monitor: High Trip exceeded Which ONE (1) of the following describes the resulting ventilation alignment?

A. Fuel Building normal supply and exhaust fans are tripped. Fuel Building Essential PACUs take suction from the Fuel Building atmosphere and discharge back to the Fuel building atmosphere.

B. Fuel Building normal supply fan trips. Fuel Building normal exhaust fan remains running. Fuel Building Essential PACUs take suction from the Fuel Building intake dampers and discharge downstream of the Fuel Building normal exhaust fan.

C. Fuel Building normal supply fan trips. Fuel Building normal exhaust fan remains running. Fuel Building Essential PACUs take suction from Fuel Building Intake dampers and discharge back to the Fuel building atmosphere.

D. Fuel Building normal supply and exhaust fans are tripped. Fuel Building Essential PACUs take suction from the Fuel Building intake dampers and discharge downstream of the Fuel Building normal exhaust fan.

Answer: A

Reference:

Question Source: Bank # __X ___

Modified Bank # _______

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 072K4.03 072K4.03 Importance Rating 3.2 3.6 Tier # 2 2 Group # 1 1

Question 59 Given the following conditions:

Unit 2 is operating at 98% power

The Hotwell Sampling System detects a leak from the Circulating water system.

The Overboard System is in automatic and all four Condensate Pumps are running.

Which ONE (1) of the following describes the effects on the plant?

A. The condensate pump on the affected quadrant is automatically secured. The Overboard System dumps the affected quadrant until correct chemistry is restored. A manual bypass valve is opened to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding. Power must be reduced to less than 95%.

B. The affected quadrant is automatically isolated. The Overboard System dumps the affected quadrant until correct chemistry is restored. A manual bypass valve is opened to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding. Power must be reduced to less than 75%.

C. The affected quadrant is automatically isolated. The Overboard System dumps the affected quadrant until correct chemistry is restored. A bypass valve automatically opens to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding Power must be reduced to less than 75%.

D. The affected quadrant is automatically isolated. The Overboard System dumps the affected quadrant until correct chemistry is restored. A bypass valve automatically opens to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding Power must be reduced to less than 85%.

Answer: B

Reference:

SD-SO23-240 Question Source: Bank # ___ ___

Modified Bank # _______

New _ X___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 056A2.04 056A2.04 Importance Rating 2.6 2.8 Tier # 2 2 Group # 1 1

Question 60 Given the following conditions:

A LOCA has occurred on Unit 2.

RCS pressure is 600 psia and dropping slowly.

Pzr level is 12% and lowering slowly.

S/G levels are 21% NR slowly rising.

All ECCS equipment is operating as required.

Which ONE (1) of the following describes the ECCS flow indication?

A. Constant HPSI flow with no LPSI flow.

B. Rising HPSI flow with no LPSI flow.

C. Constant HPSI and LPSI flow.

D. Rising HPSI and rising LPSI flow.

Answer: B

References:

Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 002K1.08 002K1.08 Importance Rating 4.5 4.6 Tier # 2 2 Group # 2 2

Question 61 Given the following conditions:

A small break Loss of Coolant Accident has occurred.

High Pressure Safety Injection (HPSI) Pump P017 has tripped on over current.

The crew aligned and started HPSI Pump P018.

Two charging pumps are running.

Pressurizer pressure is 1500 psia and steady.

HPSI Pumps P018 and P019 were secured upon meeting the requirements of FS-7, HPSI Throttle/Stop Criteria.

PZR level indicates 20% and DROPPING SLOWLY.

Which ONE (1) of the following describes the action required?

A. Start HPSI Pump P018 and throttle open enough HPSI Injection valves to raise Pressurizer level to at least 28%.

B. Start HPSI Pump P018 and P019 and the third Charging Pump and fully open all HPSI Injection valves.

C. Start HPSI Pumps P018 and/or P019 and fully open enough HPSI Injection valves to raise Pressurizer level to at least 28%.

D. Start HPSI Pumps P018 and/or P019 and throttle open HPSI Injection valves.

Answer: D

Reference:

Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 006K6.03 006K6.03 Importance Rating 3.6 3.9 Tier # 2 2 Group # 2 2

Question 62 Given the following conditions:

Unit 2 is in Mode 3

LV-0110A, letdown flow control valve in service

PV-0201A, letdown back pressure control valve in service

Pressurizer Level Control System master controller in "MANUAL" with letdown flow at 38 gpm.

Charging pump P-190 is in service

Pulsation dampener adjustment in progress on pumps P-191 and P-192.

Backpressure controller PIC-0201A output FAILS TO ZERO while in "AUTO".

Pressurizer level is observed to slowly DROP.

Which ONE (1) of the following identifies the reason for the pressurizer level change?

A. A small void in the reactor vessel upper head is now being compressed.

B. Zero output from PIC-0201A in "AUTO" corresponds to 30gpm flow.

C. A small break has developed in the pressurizer steam space.

D. A pressure relief valve is lifting to the miscellaneous waste tank, T063.

Answer: D

Reference:

Question Source: Bank # __X ___

Modified Bank # ___ ___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 010K4.03 010K4.03 Importance Rating 3.8 4.1 Tier # 2 2 Group # 2 2

Question 63 Given the following conditions:

Unit 2 is at 70% power.

Tcold is 539ºF

Thot is 576ºF

Pzr Level is on program

A fault in the SBCS results in the bypass valves opening to pass an additional 10%

steam flow.

o Pzr level is now 38%

o Tcold is 535.5º F o Thot is 577.5º F Which ONE (1) of the following describes the response of the Pressurizer Level Control System?

A. Both backup charging pumps will be running with minimum letdown flow.

B. Only the first backup charging pump will be running with minimum letdown flow.

C. Only the first backup charging pump will be running with letdown flow reduced but still greater than minimum.

D. No change in the Pzr Level control system, the SBCS is designed to accommodate up to 40% change in Rx Power.

Answer: A Provide pressurizer level program curve and Tcold program curve for reference Question Source: Bank # ___ ___

Modified Bank # _______

New _ X ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 011A3.02 011A3.02 Importance Rating 2.6 2.8 Tier # 2 2 Group # 2 2

Question 64 Given the following conditions:

o Unit 2 is operating at 100% power.

o The shaft on RCP P-004 shears o Due to a fault in the Reactor Protection System circuitry, the Turbine Trip coils fail to energize Assuming no action by the crew, which ONE (1) of the following describes the effect of this malfunction?

A. An uncontrolled cool down of the RCS, resulting in less shutdown margin.

B. A High Linear power trip limit to be exceeded which will trip the reactor.

C. High local power density limits to be exceeded resulting in fuel damage.

D. An increase in RCS pressure, possibly resulting in the Pressurizer safety valves lifting.

Answer: A Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 012K3.02 012K3.02 Importance Rating 3.2 3.3 Tier # 2 2 Group # 2 2

Question 65 Given the following conditions:

Group 5 CEA's have just been withdrawn to 100 inches when the following alarms and indications occur:

Group deviation alarm on PMS

Reactor power DROPPING

CEA 16 Lower Electrical Limit (LEL) light on the CEDMCS Panel is illuminated

Pulse counter indicates group 5 and CEA 16 at 100 inches

Both CEACs indicate CEA 16 at 0 inches

CEA bottom light on the core mimic is NOT illuminated CEA 16 has:

A. dropped/slipped and actual position cannot be determined.

B. NOT dropped/slipped; however, one 0 inch Reed Switch Position Transmitter (RSPT) has failed closed.

C. NOT dropped/slipped; however, both 0 inch Reed Switch Position Transmitter's (RSPT's) have failed closed.

D. dropped/slipped to position 0 inches.

Answer: D

Reference:

Question Source: Bank # ___X ___

Modified Bank # ___ ___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 014K5.04 014K5.04 Importance Rating 2.8 3.3 Tier # 2 2 Group # 2 2

Question 66 Given the following conditions:

Unit 3 is at 100% power

The S/G level selection for both FWCS are in the "BOTH" position

Control channel level transmitter LT-1111 for FWCS #1 fails to 100%

Assuming no action by the crew, which ONE (1) of the following describes the effect, if any, on the plant?

A. A Reactor Trip on high E089 S/G level.

B. A Reactor Trip on low E089 S/G level.

C. No impact, since selected to the "BOTH" position.

D. Level initially decreases in E089 S/G, but stabilizes above the Reactor Trip Setpoint.

Answer: B

Reference:

SO23-250 Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 016A2.03 016A2.03 Importance Rating 3.0 3.3 Tier # 2 2 Group # 2 2

Question 67 Given the following conditions:

The reactor is tripped.

SIAS is actuated.

A steam line break is occurring in the containment.

Containment pressure is 10 psig and rising.

A loss of Bus 2A04 has occurred.

WHICH ONE of the following is correct concerning the Containment Spray (CS) System?

A. CS Pump P-012 is on. CS Pump P-013 is on. HV-9367 open. HV-9368 open.

B. CS Pump P-012 is off. CS Pump P-013 is on. HV-9367 closed. HV-9368 open.

C. CS Pump P-012 is off. CS Pump P-013 is on. HV-9367 closed. HV-9368 closed.

D. CS Pump P-012 is on. CS Pump P-013 is off. HV-9367 open. HV-9368 closed.

Answer: C

References:

SO23-740 Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 026A3.01 026A3.01 Importance Rating 4.3 4.5 Tier # 2 2 Group # 2 2

Question 68 Given the following conditions:

It is currently 0830 8 December 2003

Unit 2 is at 100% power

Preparations for commencing a Mini Purge of containment are in progress.

An entry into containment is planned for 10 December 2003 at 1030.

When the Wide Range Gas Monitor, (WRGM) 2RE-7865 is aligned to the Containment Purge Stack, annunciator 61A08, "Airborne Radiation Hi" is received due to a fault in the circuitry.

In accordance with SO 23-3-2.34, Containment Access Control, Inspections, and Airlock Operation, which ONE (1) of the following states the LATEST time that the purge can commence without impacting the containment entry?

A. 2230 9 December 2003.

B. 1030 8 December 2003 C. 0030 10 December 2003 D. 1030 9 December 2003.

Answer: D

References:

SO 23-3-2.34 Containment access control, Inspections and airlocks operation Question Source: Bank # __ ___

Modified Bank # ___ __

New __X _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 029K3.02 029K3.02 Importance Rating 2.9 3.5 Tier # 2 2 Group # 2 2

Question 69 Given the following conditions:

Unit 2 is in MODE 6 with spent fuel pool (SFP) cooling in operation.

Annunciator 61C03, SPENT FUEL POOL LO LEVEL, goes into alarm.

Spent Fuel Pool temperature is stable.

Which ONE (1) of the following describes the response of the Spent Fuel Pool Cooling System?

A. Spent fuel pool low level alarm will alarm in the Control room and locally and the spent fuel pool makeup pump will start.

B. Spent fuel pool low level alarm will alarm in the Control room, spent fuel purification pump will stop.

C. Spent fuel pool low level alarm will alarm in the Control room and an alarm will sound locally.

D. Spent fuel pool low level alarm will alarm in the Control room and the spent fuel cooling pumps will stop.

Answer: C

References:

Question Source: Bank # ___ ___

Modified Bank # ___ X__

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 033A1.02 033A1.02 Importance Rating 2.8 3.3 Tier # 2 2 Group # 2 2

Question 70 Given the following conditions:

Unit 3 Reactor Trip has occurred.

S/G E089 Level indicates 28% NR.

S/G E088 Level indicates 36% NR.

S/G E089 Pressure is 890 psia.

S/G E088 Pressure is 1100 psia.

Annunciator "SG 2 > SG 1 PRESS CH TRIP" is received.

If both S/G Levels DECREASED to < 21% NR, which ONE (1) of the following describes the operation of the Auxiliary Feedwater (AFW) System?

AFW would automatically feed...

A. ONLY S/G E089.

B. ONLY S/G E088.

C. BOTH S/Gs because of low S/G levels.

D. ONLY S/G E089 UNTIL S/G E088 pressure equals 950 psia, then BOTH.

Answer: C Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 035K1.01 035K1.01 Importance Rating 4.2 4.5 Tier # 2 2 Group # 2 2

Question 71 Bled Steam and Live Steam tube bundles have been isolated on the Moisture Separator Reheaters due to leakage.

What is the MAXIMUM plant power level that can be maintained and the basis for this precaution.

A. 90%, Reduced Rankine cycle efficiency.

B. 85%, Increase in LP Turbine windage due to greater quantity of steam going through the turbine.

C. 90%, reduced preheating of the feedwater.

D. 85%, Increased moisture in the steam going to the LP Turbine.

Answer: A

Reference:

SO23-160, SO23-9-1 Question Source: Bank # ___ ___

Modified Bank # __X ___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 039K1.08 039K1.08 Importance Rating 2.5 2.7 Tier # 2 2 Group # 2 2

Question 72 Given the following plant conditions:

The plant is at 100% power.

Condenser Vacuum Pump hand switch HS-3331A (CR-53) is in AUTO.

Condenser Vacuum starts to degrade slowly and is at approximately 4 in Hg absolute pressure.

Which ONE (1) of the following describes the design of the Condenser Vacuum System that will prevent continued degradation of Condenser vacuum?

A. PV3335B will OPEN and PV3335A will CLOSE placing the Air Assisted Air Ejectors in service.

B. Condenser Vacuum Pump will shift to the "Hogging" mode of operation and prevent further loss of vacuum.

C. Condenser Vacuum Pump will startup and will be operating in the "Hogging" mode after the inlet diaphragm valves are opened.

D. PV3335A will OPEN and PV3335B will CLOSE placing the Air Assisted Air Ejectors in service.

Answer: A.

References:

SO23-190 Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 055K3.01 055K3.01 Importance Rating 2.5 2.7 Tier # 2 2 Group # 2 2

Question 73 Given the following conditions:

A Station Blackout has occurred.

The diesel generators have both failed to start.

SO23-12-1 Standard post trip Actions steps 1 through 10 have been completed

Diagnosis of Station Blackout has been verified

Actions have been taken to notify the Shift Manager of the situation

The Emergency plan has been initiated In accordance with SO 23-12-8, Station Blackout, which ONE (1) of the following describes the FIRST action taken by the crew?

A. Initiate SO23-12-11, Attachment 8, Restoration of Offsite Power.

B. Restore and maintain at least one (1) S/G level between 30% and 80% NR C. Bleed steam as necessary to maintain S/G pressure 1100 psia using ADVs D. Attempt to energize 1E 4KV bus A04 or A06 from the other unit.

Answer: A

References:

SO23-12-8, Station Blackout Step 4 Question Source: Bank # ___ ___

Modified Bank # ___ ___

New _ X ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 062G2.4.16 062G2.4.16 Importance Rating 3.0 4.0 Tier # 2 2 Group # 2 2

Question 74 Given the following conditions:

Unit 3 is operating at 100% power.

Pzr Level is 53%

Maintenance is in progress in the B001 Battery room.

Salt Water Cooling (SWC) pumps 3P112 and 3P113 are running

125 VDC bus D1 is de energized due to a fault.

Which ONE (1) of the following describes the effect on the Unit 3 SWC system?

A. SWC pump 3P112 breaker will trip on loss of control power and the standby SWC pump P307 will start.

B. SWC pump 3P112 breaker will remain shut, but there will be no remote operation or automatic tripping available.

C. SWC pump 3P113 breaker will trip on loss of control power and the standby SWC pump P114 will start.

D. SWC pump 3P113 breaker will remain shut, but there will be no remote operation or automatic tripping available.

Answer: B

Reference:

SO23-6-15 Attachment 13 SO23-140 125 and 250 VDC Systems Question Source: Bank # ______

Modified Bank # ___X__

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 063K2.01 063K2.01 Importance Rating 2.9 3.1 Tier # 2 2 Group # 2 2

Question 75 Given the following conditions:

A plant trip has occurred and offsite power to both vital 4.16kv buses has been lost.

During Standard Post Trip Actions the ACO observes the following:

o DG `G002' has tripped on overspeed.

o DG `G003' has started but its output breaker has not closed.

o DG `G003' voltage is 3.98KV

All other indications appear normal.

Which ONE (1) of the following actions is required in accordance with the procedure in progress?

A. Emergency Stop the `G003' Diesel Generator.

B. Adjust the output voltage to 4.36KV and close the G003 output breaker.

C. Reset the 86 Lockout; adjust voltage and close the G003 output breaker.

D. Direct an Auxiliary Operator to reset 'G002' Diesel Generator.

Answer: B

Reference:

SO23-13-11, Attachment 6 step 6a Question Source: Bank # ______

Modified Bank # ___X __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 064A1.03 064A1.03 Importance Rating 3.2 3.3 Tier # 2 2 Group # 2 2

Question 76 The Process Radiation Monitoring System generates an alarm signal in the control room to perform specific isolation functions.

Which ONE (1) of the following isolation signals are generated by the Process Radiation Monitoring System?

A. Containment Isolation.

B. Containment Purge Isolation.

C. CCW Non Critical Loop Isolation.

D. Radwaste Building Ventilation Isolation.

Answer: B

Reference:

Question Source: Bank # ___X___

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 073A4.01 073A4.01 Importance Rating 3.9 3.9 Tier # 2 2 Group # 2 2

Question 77 Which ONE (1) of the following describes the power supplies for the Nuclear Service Water Pumps P-138 and P-139?

A. 480V Bus 3B07 and 480V 3B14 B. 480V Bus 2A06 and 480V 3A06 C. 480V Bus 2A04 and 480V 3A04 D. 480V Bus 2B07 and 480V 2B14 Answer: D

Reference:

SO23-450 Question Source: Bank # ___X__

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 075K2.03 075K2.03 Importance Rating 2.6 2.7 Tier # 2 2 Group # 2 2

Question 78 The purpose/function of the Respiratory/Service Air System (RSAS) includes all of the following EXCEPT:

A. To provide compressed air to service outlets throughout the plant and Make-up Demineralizer area for operation of pneumatic tools and other service requirements.

B. To inflate and maintain the spent fuel pool seals.

C. To provide compressed air at a normal pressure of 115 psig and meet OSHA Class D breathing air requirements.

D. To provide a backup source of compressed air for the safe shutdown of the plant in the event of a failure of the Instrument air system.

Answer: D

Reference:

SO23-570 Question Source: Bank # ___ ___

Modified Bank # ___ __

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 079G2.1.27 079G2.1.27 Importance Rating 2.8 2.9 Tier # 2 2 Group # 2 2

Question 79 Given the following conditions:

Unit 2 is at 100% power

Unit 3 is at 60% power, increasing to 100%.

There is a leak in the wet fire protection main system pressure has dropped to 106 psig and is holding steady.

Which ONE (1) of the following statements describes the combination of fire pumps that are running to maintain Fire Protection Header Pressure?

A. One jockey pump and fire pump P-220 B. Two jockey pumps and fire pump P-221 C. Two jockey pumps and fire pump P-222 D. One jockey pump, fire pump P-221 and P-222 Answer: B

Reference:

SO23-590 Fire Protection System Question Source: Bank # ___ ___

Modified Bank # ___ __

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 086A2.02 086A2.02 Importance Rating 3.0 3.3 Tier # 2 2 Group # 2 2

Question 80 Given the following conditions:

Unit 2 is in MODE 5

LPSI Train A is providing Shutdown Cooling using HX ME-003

Shutdown Cooling Heat Exchanger inlet temperature indicates 152º F on TR-8148

A 10º F/hr cooldown is in progress.

The CRS directs that RCS temperature be stabilized.

Which ONE (1) of the following describes the preferred action(s) to stop the cooldown?

A. Throttle CLOSED the SDC HX ME-003 outlet to RCS Loops lA/1B (HV-9322)

B. Adjust the SDC HX ME-003 outlet valve (HV-8150)

C. Fully OPEN the bypass valve (HV-8160) to bypass SDC HX ME-003 D. Adjust CCW temperature to SDC HX ME-003 using CCW-HCV-6547 Answer: B

References:

SO23-3-2.6 SO23-5-1.5 Question Source: Bank # __X___

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 005A1.01 005A1.01 Importance Rating 3.5 3.6 Tier # 2 2 Group # 3 3

Question 81 Given the following conditions:

Component Cooling Water (CCW) Pumps P-024 and P-026 are operating

CCW Pump P-025 is aligned to Train A and is in STANDBY

Grid instabilities result in a loss of off site power

The reactor has tripped

Pzr level is 15% and rising

Pzr Pressure is 1580 psia and rising slowly

The Emergency Diesels have started normally.

Assuming NO action by the crew, which ONE (1) of the following correctly describes the status of the CCW pumps?

A. All CCW pumps are running B. CCW Pumps P-024 and P-026 are running, P-025 is off C. CCW Pumps P-024 and P-025 are running, P-026 is off D. CCW Pumps P-025 and P-026 are running, P-024 is off Answer: D Question Source: Bank # ______

Modified Bank # ___X__

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 008K4.09 008K4.09 Importance Rating 2.7 2.9 Tier # 2 2 Group # 3 3

Question 82 Given the following conditions:

The plant is in Mode 1, 100% power

It has been determined that the Trisodium Phosphate baskets in containment were inadvertently emptied during the last outage.

IF a LOCA were to occur, which ONE (1) of the following describes the consequences of this action?

INCREASED:

A. containment pressure.

B. formation of oxygen.

C. containment iodine levels.

D. formation of hydrogen.

Answer: C Question Source: Bank # __X__

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 027K1.01 027K1.01 Importance Rating 3.4 3.7 Tier # 2 2 Group # 3 3

Question 83 Given the following conditions:

Core reload is in progress.

Refueling Machine over core with fuel assembly grappled.

Which ONE (1) of the following states the safe location for placement of the assembly suspended on the Refueling Machine grapple IF the Spent Fuel Handling Machine loses power?

A. In designated core location.

B. In most easily accessible core location.

C. Up-ender in horizontal position.

D. Lowered into deep area of refueling pool.

Answer: A Question Source: Bank # __ X __

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _ X __

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 034A2.03 034A2.03 Importance Rating 3.3 4.0 Tier # 2 2 Group # 3 3

Question 84 Given the following conditions:

Unit 2 is at 100% power.

PZR pressure is 2250 psia

Tcold is 539º F

The selected steam pressure instrument input into SBCS fails HIGH.

The reactor subsequently tripped.

Assuming NO action by the crew, which ONE (1) of the following is the response of the Atmospheric Dump Valves and Steam Bypass Control Valves over the next ten (10) minutes?

A. Atmospheric dump valves OPEN.

Steam Bypass Control valves OPEN.

A. Atmospheric dump valves OPEN.

Steam Bypass Control valves remain CLOSED.

B. Atmospheric dump valves remain CLOSED Steam Bypass Control valves remain CLOSED.

C. Atmospheric dump valves remain CLOSED.

Steam Bypass Control valves OPEN.

Answer: D

References:

SO23-175 Question Source: Bank # __ ___

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 041K6.03 041K6.03 Importance Rating 2.7 2.9 Tier # 2 2 Group # 3 3

Question 85 Given the following conditions:

Unit 3 is at 100% power.

All control systems in AUTO.

The Main Turbine Generator trips on a voltage regulator card failure.

Assuming no operator action, which ONE (1) of the following describes the secondary plant response immediately following the occurrence?

A. Main Steam safeties lift and modulate. FWCS 1 and 2 CLOSE the feedwater isolation valves.

B. SBCS valves modulate open, FWCS 1 and 2 control feedwater isolation valves in Reactor Trip Override. (RTO)

C. Main Steam Safety valves lift, FWCS 1 and 2 feed the S/Gs to high level override setpoint.

D. SBCS valves modulate open, FWCS l and 2 close the feedwater regulating valves.

Answer: D

References:

Question Source: Bank # __ ___

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 045K3.01 045K3.01 Importance Rating 2.9 3.2 Tier # 2 2 Group # 3 3

Question 86 Which one (1) of the following describes the alignment of cooling water to an Instrument Air Compressor when it is secured and the reason for this alignment?

A. TPCW flow is throttled at 60 gpm to prevent overheating of the compressor cylinders.

B. TPCW flow is automatically isolated to the compressor by a solenoid valve to prevent overcooling of the compressor cylinders C. TPCW flow is throttled to provide an inlet pressure of 60 psig to prevent overheating of the compressor cylinders D. TPCW flow remains unchanged so that compressor is aligned for automatic restart.

Answer: B

References:

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 078K1.04 078K1.04 Importance Rating 2.6 2.9 Tier # 2 2 Group # 3 3

Question 87 Given the following conditions:

Reactor has tripped from 100% power.

Reactor coolant system pressure is 1650 psia and dropping.

Pressurizer level is 10% and dropping.

Steam generator levels have turned at 21% NR and are recovering.

Steam generator pressures are 980 psia and rising.

Containment pressure is 7.4 psig and rising.

Safety Injection and Emergency Feedwater actuations have occurred.

Assuming all systems functioned as designed, which ONE (1) of the following states the additional Engineered Safety Features Actuation(s) present?

A. Containment Spray Actuation.

B. Containment Isolation actuation C. Main Steam Isolation.

D. Containment Isolation Actuation and Main Steam Isolation.

Answer: B

References:

Question Source: Bank # __ _ __

Modified Bank # __ X ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 103 A3.01 103 A3.01 Importance Rating 3.9 4.2 Tier # 2 2 Group # 3 3

Question 88 Operating Instruction S023-2-8, "Saltwater Cooling System Operation," cautions against running a saltwater cooling (SWC) pump without its associated component cooling water loop pressurized.

Which ONE (1) of the following describes the reason for this caution?

A. Prevent thermal shock of the CCW heat exchanger.

B. Prevent saltwater from entering the CCW system in the event of a tube leak.

C. CCW system provides cooling for the SWC pump motor.

D. Ensures the CCW radiation monitor is in service in the event of CCW leakage into the SWC system.

Answer: B

Reference:

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.7 2.1.7 Importance Rating 3.7 4.4 Tier # 3 3 Group # 1 1

Question 89 Toxic gas ingress to the Control Room requires a control room evacuation and plant shutdown from outside the control room Which ONE (1) of the following identifies the ORDER in which the "IMMEDIATE ACTIONS" for AOI SO23-13-2, "Shutdown From Outside the Control Room" are to be completed?

A. 1) Manually trip the reactor

2) Manually initiate MSIS.

3) Select manual and stop all Charging Pumps.

B. 1) Manually trip the reactor

2) Manually initiate MSIS.

3) Select manual and stop backup Charging Pumps ONLY.

C. 1) Select manual and stop all Charging Pumps.

2) Manually trip the reactor

3) Manually initiate MSIS.

D. 1) Manually trip the reactor

2) Stop all RCPs.

3) Manually initiate MSIS.

Answer: A

Reference:

AOI SO23-13-2, "Shutdown From Outside the Control Room" Question Source: Bank # __ ___

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.12 2.1.12 Importance Rating 2.9 4.0 Tier # 3 3 Group # 1 1

Question 90 Given the following conditions:

15 minutes post trip from full power operation.

The crew has completed Standard Post Trip Actions

Chemistry sample indicates elevated activity in S/G E089.

RCS pressure is 1650 psia and slowly lowering.

RCS temperature is 545º F and stable.

Pzr level 10% and lowering.

In accordance with SO23-12-4, SGTR, which ONE (1) of the following actions is required next?

A. Isolate S/G E089.

B. Initiate cooldown to Thot less than 530ºF.

C. Depressurize RCS by spraying down to backflow from S/G to the RCS.

D. Start the third charging pump to refill the Pzr.

Answer: B.

References:

Question Source: Bank # ___ ___

Modified Bank # __X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.23 2.1.23 Importance Rating 3.9 4.0 Tier # 3 3 Group # 1 1

Question 91 Given the following conditions:

Unit 2 is in MODE 6.

Swapping to a Containment Spray Pump for Shutdown Cooling per SO23-3-2.6, Att. 25 is in progress.

Step 2.1.10 of Att. 25 requires SDC flow to be adjusted to less than 2750 gpm.

Which ONE (1) of the following describes the reason that SDC flow is reduced?

A. To prevent Containment Spray Pump runout when off-going SDC pump is stopped.

B. To prevent excessive Shutdown Cooling Heat Exchanger flow rate when starting the Containment Spray Pump.

C. To prevent voiding in the Shutdown Cooling Heat Exchanger when stopping the off-going SDC pump.

D. To prevent loss of off-going SDC Pump NPSH when Containment Spray Pump is started.

Answer: A Question Source: Bank # ___X___

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.32 Importance Rating 3.4 Tier # 3 Group # 1

Question 92 For a Surveillance Test that was aborted, the:

A. Paperwork can be immediately discarded.

B. Acceptance review will be completed, noting that the ST is incomplete.

C. Acceptance review will be completed only after the complete performance of the ST.

D. Paperwork is maintained, however, the acceptance review is not required to be performed.

Answer: B Question Source: Bank # ___X___

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 2.2.12 Importance Rating 3.0 Tier # 3 Group # 2

Question 93 Technical Specification 3.4.7 restricts starting a RCP when Tcold is less than 256º F and steam generator secondary water temperature is more than 100º F above each RCS Tcold.

Which ONE (1) of the following is the reason for this limit?

A. Minimize RCS pressure transient caused by additional heat transfer from the core B. Prevent core lift from excessive differential pressure across the core.

C. Minimize RCS pressure transient caused by reverse heat transfer from a hot S/G.

D. Prevent excessive RCP starting current due to increased density of the coolant.

Answer: C Question Source: Bank # ___ ___

Modified Bank # ___X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 2.2.25 Importance Rating 2.5 Tier # 3 Group # 2

Question 94 Which ONE (1) of the following evolutions would be considered a "Core Alteration" by Technical Specifications?

A. Removing the Upper Guide Structure from the Reactor Vessel.

B. Removing the incore detectors from the Reactor vessel.

C. Transferring a CEA between the Reactor vessel and Spent Fuel Pool.

D. Uncoupling all CEAs in Shutdown Rod Group "B".

Answer: C

Reference:

Tech. Spec, Question Source: Bank # ___X___

Modified Bank # _______

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.2.27 Importance Rating 2.6 Tier # 3 Group # 2

Question 95 The Radwaste Operator is required to complete a valve lineup in an area where the radiation level is 50 mrem/hour. The operator's current Total Effective Dose Equivalent (TEDE) is 730 mrem.

What is the maximum time he can work in this area and not exceed his Administrative Dose Control Level (ADCL)?

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

C. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

D. 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months .

Answer: B.

References:

Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.3.1 2.3.1 Importance Rating 2.6 3.0 Tier # 3 3 Group # 3 3

Question 96 The Main Purge Isolation Valves do NOT receive actuation signals from SIAS and CIAS yet the Mini-Purge Isolation Valves automatically shut on either of these signals.

Which ONE (1) of the following describes why the Main Purge Isolation Valves do NOT receive either signal?

A. The Main Purge Valves are required to be in the closed position in Modes 1-4.

B. The Main Purge Valves are interlocked with the Mini-Purge Valves and that causes them to automatically shut.

C. The Main Purge Valves are interlocked with the Mini-Purge Fans and that causes them to automatically shut.

D. The Main Purge Valves will automatically shut on a CCAS (Containment Cooling Actuation Signal) which actuates due to an SIAS (Safety Injection Actuation Signal).

Answer: A Question Source: Bank # ___X___

Modified Bank # _______

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X __

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.3.9 Importance Rating 2.5 Tier # 3 Group # 3

Question 97 Unit 2 was operating at 100% power when a tube rupture occurred on E089.

Which ONE (1) of the following describes the preferred method of cooling down the RCS for SG maintenance?

A. Dump steam to the condenser using the E088 SG to minimize radiological releases.

B. Dump steam through the E088 SG's ADVs to minimize contamination of the secondary system for ALARA reasons.

C. Dump steam through the E089 SG's ADVs to reduce the contamination in the condensate.

D. Dump steam to the condenser using the E089 SG to minimize radiological releases.

Answer: A Question Source: Bank # ___ ___

Modified Bank # _______

New __X _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.3.11 Importance Rating 2.7 Tier # 3 Group # 3

Question 98 Given the following conditions

A small break LOCA is occurring.

PZR pressure 1750 psia.

Thot is 570º F

Tcold is 552º F

Core exit thermocouple temperature is 570º F

P-001 and P-004 RCP's have been manually tripped.

Which ONE (1) of the following describes the reason that two (2) RCPs were left operating under these conditions?

A. Maintaining forced circulation is desirable and the potential for RCP seal failures is reduced.

B. Maintaining 2 pumps running minimizes RCP journal bearing wear/damage.

C. Maintaining 2 pumps running minimizes the potential for the formation of boron crystals in the core.

D. Maintaining forced circulation is desirable and the plant can remain in a safe condition under these conditions.

Answer: D Question Source: Bank # ___ ___

Modified Bank # __X___

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.4.6 Importance Rating 3.1 Tier # 3 Group # 4

Question 99 During use of SO23-13-7, "Loss of CCW/SWC," the section for responding to a low level in a CCW surge tank directs that if the surge tank level transmitter is off-scale low then the actions of the section for high level in a CCW surge tank should be performed.

Which ONE (1) of the following describes the reason that these actions are performed?

A. The actual condition revealed is a high level which has compressed the gas space bubble and increased the pressure seen by the reference leg of the level detector causing it to indicate off-scale low B. This avoids redundancy and minimizes procedure length since the appropriate actions for a high surge tank level are identical to those for a low surge tank level.

C. Because the off-scale low indication will result in a continuous automatic makeup to the CCW surge tank, taking the actions for a high level condition will be appropriate as the surge tank fills.

D. The actual condition revealed is a high level which has filled the normally dry reference leg with water resulting in indicated level being off-scale low.

Answer: D Question Source: Bank # __X___

Modified Bank # __ __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.4.24 Importance Rating 3.3 Tier # 3 Group # 4

Question 100 SO23-13-21, "Fire" describes the duties and responsibilities of personnel during a fire. A fire is reported inside the protected area of San Onofre Unit 2.

Which ONE (1) of the following correctly describes the duties of the Designated Licensed Operator, after obtaining a copy of the zone evaluation?

A. Remain in the control room, and coordinate the fire fighting effort.

B. Remain in the control room, and act as technical advisor.

C. Proceed to the scene, and act as technical advisor.

D. Proceed to the scene, and act as fire brigade leader.

Answer: C

Reference:

Question Source: Bank # __ X__

Modified Bank # __ __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.4.27 Importance Rating 3.0 Tier # 3 Group # 4

2PIC-0100 PZR PRESSURE CONTROL MEASUREMENT SELECTED VIA 2HS0100 (2PT100X OR 2PT100Y)

OPERATOR 2500 PSIA SETPOINT VALVE PIC-0100 (1500-2500 PSIA)

OSP 2263 2500 PSIA LOCAL ALARM/REMOTE (1500-2500 PSIA) ACTUATION AT:

HA = MEAS < 2275 PSIA (77.5%)

RESETS AT 2265 PSIA (76.5%)

CONTROLLER OUTPUT OUT 100.0 (0-100.0%)

AM E

A/M SEL ACK 100%

CONTROLLER OUTPUT 0%

33.3% 66.7% 100%

PROPORTIONAL SPRAY HEATERS VALVES 100% TO 0% 0-100%

FIGURE III-6: PRESSURIZER PRESSURE CONTROLLER PIC-0100

NUCLEAR ORGANIZATION OPERATING INSTRUCTION SO23-3-1.7 UNITS 2 AND 3 REVISION 24 TCN 24-1 PAGE 102 OF ATTACHMENT 4 RCP MINIMUM PRESSURE FOR OPERATION

NUCLEAR ORGANIZATION OPERATING INSTRUCTION SO23-3-1.7 UNITS 2 AND 3 REVISION 24 TCN 24-1 ATTACHMENT 5 RCP MINIMUM PRESSURE FOR OPERATION - LOW TEMPERATURE/PRESSURE

FIGURE III-2A: PRESSURIZER LEVEL CONTROL PROGRAM 60 P

R (566EF, 53%)

E S

S 50 U

R I

Z E

R 40 L (547EF, 38%)

E V

E 30 L

20 550 560 570 580 590 RCS AVERAGE TEMPERATURE (EF)

FIGURE III-2B: PRESSURIZER LEVEL CONTROL SETPOINT PROGRAM

ML040210270

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