ML032480906

Proposed Facility - Developed RO Written Exam for the Fermi Retake Examination - July 7, 2003

ML032480906
Person / Time
Site:	Fermi
Issue date:	07/07/2003
From:	Lanksbury R NRC/RGN-III/DRS/OLB
To:	O'Connor W Detroit Edison
References
50-341/03-302
Download: ML032480906 (76)

Text

PROPOSED FACILITY-DEVELOPED RO WRITTEN EXAM FOR THE FERMI RETAKE EXAMINATION -JULY 7,2003

Question #I Details EQ-OP-315-0104-000-B004-001 NRC RO Retake 2003 Question Text The following initial conditions exists at 09:OO:OO 0 Reactor Power ..................... 100%

0 Total core flow .................... 98 Mlbm/hr 0 Recirc Pump "A"speed ........85%

0 Recirc Pump "B" speed........84%

The following events occur:

0 09: 1O:OO ..........Breaker 65G-G3 trips open 0 09: 10:20..........Recirculation Pump "A" trips 0 09: 12:OO..........Loss of Heater Drains due to power reduction At 09:20:00, with no operator action, what is the indicated demand on the RR MG Set Speed Controllers?

Response A LOOPA - 40% , LOOPB - 40%

40% is the setpoint for the 213 Limiter, which is not in effect.

Response B - Correct Answer LOOPA - 28% , LOOPB - 75%

References I,& 3,4 Response C LOOPA - 28% , LOOPB - 40%

Loop A would be at 28%due to failed breaker being open, 40% is the setpoint for the 213 Limiter, which is nut in effect.

Response D LOOPA - 75% ,LOOPB - 28%

These are backwards from the correct answer.

Author: BOLLINGER Keywords: RRS Not Archived Date Last Used: 5/16/2002 -RO retake 2001 Time: 2 Question ID: 34697 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value a RO El ILO 295001 A I .01 3.5 3.6 0 SRO [7 ESP STAC PartA

References:

STAl 0 PartB ST-OP-315-0004-001 LOR 0 OpenRef.

23.138.01 [7 NOC Close Ref.

0 IN0 0 Static

Question #2 Details EQ-OP-315-0165-000-B007-002 NRC RO Retake 2003 Question Text The plant was operating at 100% when a loss of offsite power occurred. The following conditions exist:

e Drywell Pressure is 1.89 psig e EDG 13 has failed to start.

What ECCS equipment will be unavailable?

Response A Core Spray Pump A and RHR Pump A EDG 11 supplies these pumps.

Response B - Correct Answer Core Spray Pump B and RHR Pump B Reference 1 Response C Core Spray Pump C and RHR Pump C EDG 32 supplies these pumps.

Response D Core Spray Pump D and RHR Pump D EDG 14 supplies these pumps.

Author: BOLLINGER Keywords: EDG Not Archived Date Last Used:

Time: 0 Question ID: 34698 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO El ILO 295003 K1.04 3.1 3.2 c] SRO ESP STAC c] PartA

References:

STAl c] PartB ST-OP-315-0065-01 c] LOR 0 OpenRef.

0 NOC 0 Close Ref.

0 IN0 0 Static

Question #3 Details EQ-OP-315-0164-000-C002-001 NRC RO Retake 2003 Question Text The plant is operating at 55% Reactor power when 260/130VDC BOP power is lost.

Select the statement that correctly describes the plant response.

Response A Power is lost to the RCIC logic circuit which will result in RCIC failing to auto start on a valid initiation signal.

RClC logic circuit is powered from ESF DC.

Response B - Correct Answer Power is lost to the Main Turbine Trip circuits resulting in a Main Turbine Trip and a Reactor Scram.

Reference -1 Response C The running Turbine Lube Oil pumps will trip causing a Main Turbine Trip and a Reactor Scram.

The running Turbine Lube Oil Pumps are AC powered, not affected by loss of DC.

Response D Loss of Feedwater to the Reactor vessel due to closure of Reactor Feed pump speed governor.

Governor is electrohydraulic - oif from an AC pump: power from UPS.

Author: BOLLINGER Keywords: Not Archived Date Last Used: 6/6/2000 Time: 0 Question ID: 34699 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO 0 ILO 295004 K3.03 3.1 3.5 0 SRO 0 ESP STAG 0 PartA

References:

STAl c] PartB ST-OP-315-0164-001 0 LOR OpenRef.

17 NOC a Close Ref.

IN0 0 Static

Question #4 Details EQ-OP-315-Ol27-OOO-CO13-OO2 NRC RO Retake 2003 Question Text The plant is at 100% power when the following conditions occur:

0 Main Turbine trips 0 Bypass Valves open 0 ARI air supply valves are open 0 ARI vent valves are closed The reactor will scram in anticipation of the rapid:

Response A - Correct Answer INCREASE in thermal power References - l32 Response B INCREASE in reactor water level This is opposite of what actually happens.

Response C DECREASE in reactor water level Level will decrease, but RPS doesnt SCRAM in anticipation of lowering level.

Response D DECREASE in main steam line pressure Pressure would actually INCREASE.

Author: BOLLINGER Keywords: RPS Not Archived Date Last Used:

Time: 0 Question ID: 34703 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value a RO 0 ILO 295005 K1.01 4.0 4.1 0 SRO 0 ESP 0 STAC 0 PartA

References:

STAl PartB ST-OP-315-0028-001 0 LOR 0 OpenRef.

ST-OP-315-0027-001 0 NOC a Close Ref.

0 IN0 Static

Question #5 Details EQ-OP-315-0127-000-8002-002 NRC RO Retake 2003 Question Text The plant is operating at 100%with the following conditions:

Recirc Pump A Setpoint.................................... 88.9%

Recirc Pump B Setpoint .................................... 83.6%

Core Flow......................................................... 98.5 X 106 lb/hr Reactor water Level .......................................... 172 inches Reactor Pressure ............................................... 1020 psig North Reactor Feed Pump................................. 4580 rpm, increasing South Reactor Feed Pump................................. 4620 rpm, increasing Based on these conditions, what action should the operator take?

Response A Lower the Recirc Pump A Speed The difference between the two can be up to 5%, but the action is still not correct for these conditions.

Response B - Correct Answer Place the Mode Switch in Shutdown Reference 1 Response C Start the Standby Feedwater pumps This would be correct for a loss of Reactor Feed Pump, but both are running.

Response D Initiate a rapid power reduction Not correct when trip setpoint is exceeded.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34704 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value 0 RO a ILO 295006 A2.05 4.6 4.6 17 SRO 0 ESP 0 STAC 0 PartA

References:

0 STAl PartB ST-OP-315-0127-001 0 LOR OpenRef.

0 NOC a Close Ref.

0 IN0 0 Static

Question #6 Details EQ-OP-315-0127-000-B002-003 NRC RO Retake 2003 Question Text Which of the following will result in an Automatic Reactor scram?

Response A Drywell Pressure of 1.63 psig.

Scram setpoint is 1.68 psig.

Response B Reactor Vessel Low Water Level of 180 inches.

Scram setpoint is 173 inches.

Response C - Correct Answer APRM Fixed Neutron Flux Upscale of 118%.

Reference - 1 Response D Reactor Vessel Steam Dome Pressure of 1045 psig.

Scram setpoint is 1093 psig Author: BOLLINGER Keywords: RPS Not Archived Date Last Used:

Time: 0 Question ID: 34705 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value a RO El 110 295006 K2.06 4.2 4.3 0 SRO 0 ESP STAG PartA

References:

STAl PartB ST-OP-315-0027-001 0 LOR Open Ref.

0 NOC Close Ref.

IN0 Static

Question #7 Details EQ-OP-802-2017-000-0001-010 NRC RO Retake 2003 Question Text The Control Room (CR) has become uninhabitable. As a result, the plant has entered 20.000.19, Shutdown From Outside the Control Room.

The transfer of certain CR controls to outside the CR is needed to.. ..

Response A preclude the effects of hot shorts.

This is true for Dedicated shutdown Panel, not Remote.

Response B - Correct Answer continue shutdown and cooldown.

References - ST-OP-315-0044 Response C allow proper fire fighting response.

Firefighters have nothing t o do with the switches transferred.

Response D allow rapid re-entry into the CR.

although the AOP override says to move back into the CR when feasible, thats not why the switches are transferred.

Author: BOLL1NG ER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34706 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO 295016 K3.03 3.5 3.7 SRO 0 ESP 0 STAC 0 PartA

References:

0 STAl 0 part^

ST-OP-315-0044 0 LOR 0 OpenRef.

0 NOC Close Ref.

0 IN0 0 Static Page: 1

Question #8 Details EQ-OP-202-0901-OOO-AOOl-O31 NRC RO Retake 2003 Question Text The plant is operating at 100% with the following conditions:

North TBCCW pump ................................... tripped Center TBCCW pump ................................ ..running Stator Cooling Water Outlet Temperature ....173'F and rising Attempts to start the South TBCCW pump have been unsuccessful.

What actions should be taken?

Response A Perform a rapid power reduction This would be true if the outlet temperature had not already been exceeded.

Response B Increase GSW flow to the Stator Cooling Water heat exchanger GSW cools TBCCW which cools Stator Cooling, GSW doesn't cool Stator Cooling.

Response C - Correct Answer Trip the Reactor and Main Turbine Reference - 2 Response D Attempt a restart of the North TBCCW pump While plausible, the outlet temperature has been exceeded, per the override.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34712 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO El ILO 295018 2.4.50 3.3 3.3 SRO 0 ESP

References:

0 STAC PartA 20.128.01 STAl I7 Part6 LOR 0 Open Ref.

0 NOC a Close Ref.

17 IN0 Static

Question#9 Details EQ-OP-802-2001-000-R005-001 NRC RO Retake 2003 Question Text The plant experienced a Station Blackout and all Station Air Compressors (SAC) stopped.

Instrument Air pressure has decreased to 72 psig.

Power has since been restored, and you have been directed to start the West SAC.

When the West SAC is started, it fails to load.

Why did the West SAC fail to load, and what action must be taken by procedure?

Response A Instrument Air Pressure is too high to allow loading the SAC, start the SAC with Instrument Air isolated Instrument Air should be at least 75 psig to allow loading, isolating Instrument Air would defeat the purpose.

Response B Station Air Pressure is too low to allow loading the SAC, start the East SAC Instrument Air is too low, not Station Air, and the procedure directs starting with nitrogen to increase instrument Air Pressure.

Response C - Correct Answer Instrument Air Pressure is too low to allow loading the SAC, start the SAC using nitrogen bottles References -t , 2 Response D Station Air Pressure is too high to allow loading the SAC, isolate Station Air from Control Air Station Air can not be too high in this application, Control Air is already automatically isolated.

Author: BOLLINGER Keywords: COMPRESSED AIR Not Archived Date Last Used:

Time: 0 Question ID: 3471 1 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value 0 RO ILO 295019 2.1.32 3.4 3.8 0 SRO ESP 0 STAC 0 PartA

References:

STAl 0 part^

23.129 0 LOR OpenRef.

20.300.SBO NOC Close Ref.

0 IN0 0 Static

Question #IO Details EQ-OP-802-2001-000-0001-002 NRC RO Retake 2003 Question Text The plant is in Mode 4.The following conditions exist:

Division 1 RHR.. ............................................. ..Shutdown Cooling (SDC)

Division 2 RHR.. ............................................. ..NOT available.

Reactor Pressure Vessel (RPV) level.. ..................... .230 inches RPV pressure .................................................... 0 psig Division 1 RHR tripped and can NOT be restarted.

What action will the Reactor Operator be directed to perform?

Response A - Correct Answer Start Reactor Recirculation pumps Reference 20.205.01,ST-0P-315-0041 Response B Raise RPV pressure Raising pressure above 89.5 psig causes a SDC isolation Response C Lower RPV level Lowering level below L3 (173 inches) will cause a SDC isolation Response D Shift Fuel Pool Cleaning to the Reactor Well Mode 4 -head is fully tensioned - shifting FPCCU to reactor well won't cool RPV Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34735 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO la ILO 295021 A1 .05 3.0 3.0 SRO 0 ESP

References:

0 STAC 0 PartA 20.205.01 STAl 0 part^

ST-OP-315-0004 17 LOR Open Ref.

0 NOC Close Ref.

IN0 Static

Question #11 Details EQ-OP-315-0190-000-A012-001 NRC RO Retake 2003 QuestionText Select the response that correctly completes the following statement.

The refueling interlocks ensure that criticality does not occur during fuel handling operations by preventing Response A - Correct Answer control rod withdrawal whenever fuel loading equipment is over the core Reference -1 Response B control rod withdrawal whenever fuel loading equipment is energized Would not allow refueling at all, no matter the conditions Response C refueling hoist movement when fuel pool level is below 22 8 there is a TS limit of greater than 20 6, but there is no associated intertock Response D preventing withdrawal of any control rods with the Mode Switch in the REFUEL position interlocks prevent the Withdrawal of more than one control rod.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34714 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO El ILO 295023 K3.02 3.4 3.8 SRO 0 ESP STAC PartA

References:

0 STAl 0 PartB ST-OP-315-0190-001 LOR 0 OpenRef.

NOC a Close Ref.

IN0 I3 Static

Question #12 Details EQ-OP-315-0165-000-A021-002 NRC RO Retake 2003 Question Text The plant has experienced a high drywell pressure scram. HPCI is maintaining vessel level and drywell pressure is stable at 2.2 psig. The SM has directed you to remove EDG 11 from service.

What two steps are needed to accomplish this?

Response A Take Local Control of EDG 1 1; Stop EDG As long as there is a LOCA signal and the LOCA defeat switch is not bypassed, the EDG will run.

Response B Take Remote Control of EDG 11; Open EDG 11 output breaker As long as there is a LOCA signal and the LOCA defeat switch is not bypassed, the EDC will run.

Response C - Correct Answer Place EDG 11 LOCA defeat switch to bypass; Place CMC switch to OFF Reference 1 Response D Take Remote Control of EDG 11; Place CMC switch to OFF As long as there is a LOCA signat and the LOCA defeat switch is not bypassed, the EDG will run.

Author: BOLLINGER Keywords: EDG Not Archived Date Last Used:

Time: 0 Question ID: 34715 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 295024 K2.10 3.5 3.5 SRO [7 ESP

References:

0 STAC 0Part A ST-OP-315-0065 [7 STAl 0 Part B LOR Open Ref.

0NOC Close Ref.

IN0 static

Question #13 Details EQ-OP-315-0027-000-A018-001 NRC RO Retake 2003 Question Text The main turbine trips at 45% power. RPS B scram relays fail to reposition when deenergized causing a failure to scram.

ASSUMING NO OPERATOR ACTIONS, select the statement that describes the expected response to this situation.

Response A The backup scram valves associated with RPS A will energize when the RPS A scram relays trip.

Both RPS channels must trip in order to energize the valves Response B The backup scram valves associated with RPS A will deenergize when the RPS A scram relays trip.

80th RPS channels must trip in order to energize the valves Response C The alternate rod insertion valves deenergize when the high reactor pressure setpoint is exceeded on one trip unit in each trip channel.

The ARI valves eneraize o n high pressure or low level Response D - Correct Answer The alternate rod insertion valves energize when the high reactor pressure setpoint is exceeded on both trip units in one trip channel.

Reference 1,23.603 Pa. 25 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 3471 6 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value a RO a 110 295025 K2.04 3.9 4.1 a SRO 0 ESP

References:

STAC 0 Part A ST-OP-315-0021 0 STAl 0Part B ST-OP-315-0010 0LOR Open Ref.

0 NOC aClose Ref.

0 IN0 0 Static

Question #14 Details EQ-OP-802-3002-000-0001-011 NRC RO Retake 2003 Question Text The plant has experienced a full power ATWS The crew failed to initiate boron injection before Torus water temperature reached the BIIT Alternate means to shutdown the reactor have been unsuccessful.

These events could lead to exceeding the...

Response A minimum RPV flooding pressure.

Has to do with (1) the Minimum SRV Re-opening Pressure or (2) the lowesf differential pressure between the RPV and the suppression chamber at which steam flow through the Minimum Number of SRVs Required for Emergency Depressurization is sufficient to remove all decay heat from the core.

Response B - Correct Answer heat capacity limit of the containment.

Reference; ST-0P-8O2-3OO2 Response C RPV saturation limit.

The RPV Saturation Temperature is based simply on the properties of water.

Response D peak clad limit of the fuel.

The Maximum Core Uncovery Time Limit is defined to be the greatest amount of time the reactor core can remain completely uncovered and uncooled without resulting in a peak clad temperature in excess of I5OO0F.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34811 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 295026 K3.04 3.7 4.1 aSRO [7 ESP

References:

0 STAC Part A ST-OP-802-3002 STAl [7 Part B LOR Open Ref.

0 NOC Close Ref.

0 IN0 0 Static

Question #I5 Details EQ-OP-802-3004-000-0007-012 NRC RO Retake 2003 Question Text The reactor was operating at 100% power when a loss of feedwater occurred. The following conditions are observed:

RPV level is 25" and steady on wide range Drywell pressure is 1.5 psig and slowly rising Drywell temperature is 155°F and slowly rising Which one of the following actions, if taken, will prevent drywell pressure from exceeding the high drywell pressure scram setpoint?

Response A Manually shift all dual speed drywell cooling fans to low speed Shifting fans to low speed will cause temperature and pressure to increase, only 4 of 14 fans can be shifted to slow.

Response B - Correct Answer Manually start all single speed drywell cooling fans Reference ST-UP-8002-3004, 23.415 Section 5.0 Response C Manually initiate both divisions of EECW There would still only be 4 fans running in slow speed with no increased cooling of the OW.

Response D Increase GSW flow though the RBCCW Hx Although this will lower the temperature of the cooling water in the DW Coolers, there is still only 4 fans running in slow speed, which is not enough t o prevent exceeding the setpoi nt.

Author: BOLLINGER Keywords: EOP PCP Not Archived Date Last Used:

Time: 2 Question ID: 34718 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 295028 Al.04 3.9 4.0 SRO 0 ESP STAG 0 Pari A

References:

0 STAl Part B ST-OP-802-3004 LOR 0 Open Ref.

NOC ElClose Ref.

IN0 Static

Question #I 6 Details EQ-OP-315-Ol16-OOO-CO13-OO2 NRC RO Retake 2003 Question Text What is the consequence of Torus water level dropping below -1 12 inches?

Response A - Correct Answer Actuation of an SRV would directly pressurize the Torus with little or no steam condensation.

Reference ST-OP-315-0016 Response B Ensure a sufficient quantity of water to prevent excessive pool swell and flooding of the downcomers during a DBA LOCA.

This is part of the basis for upper level limit for the Torus Response C Ensure a sufficient quantity of water to prevent violation of the Vortex Limit for the HPCI and/or RCIC Pumps.

Vortex Limit applies to the LPCl pumps, not HPCI and RCIC. HPCl and RCtC use NPSH Iimits which are based on Torus temperature.

Response D Ensure a sufficient quantity of water to prevent excessive clearing loads from SRV discharges.

This is part of the basis for upper level limit for the Torus Author: BOLLINGER Keywords: CONTAINMENT Not Archived Date Last Used:

Time: 0 Question ID: 34719 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO I3ILO 295030 K2.08 3.5 3.8 aSRO 0 ESP

References:

0 STAG 0 Part A ST-OP-815-0016 0 STAl 0 Part B LOR Open Ref.

0 NOC Close Ref.

IN0 0 Static

Question #17 Details EQ-OP-315-0121-000-B006-001 NRC RO Retake 2003 Question Text Which one of the following would indicate a leak in the variable leg of a RPV Narrow Range level instrument outside containment ?

Response A Reactor Feed Pump Trip Feed pump trips on level 8 Narrow Range Response B Emergency Diesel Generator start Starts on Wide Range Level 1 Response C - Correct Answer RPV low level scram

Reference:

ST-OP-375-0021 Response D Recirc Pump Trip Trips an Wide Range Level 2 Author: BOLLINGER Keywords: RPV INST Not Archived Date Last Used:

Time: 0 Question ID: 34720 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 295031 K2.11 4.4 4.4 aSRO c]ESP STAC 0 Part A

References:

STAl 0 Part B ST-OP-315-0121-001 c]LOR 0 Open Ref.

NOC a Close Ref.

IN0 CI static

Question #18 Details EQ-0P-213-0021-000-C002-017 NRC RO Retake 2003 Question Text The plant is in an ATWS. An RO has been assigned to perform 29.ESP. 1 1, Defeat of RPV Level 1 and High Rad MSIV and Main Steam Line Drain Valve Isolation Signals. Prior to completing the procedure, the MSIVs automatically close on RPV level.

Where does the assigned operator perform the defeats for this procedure, and how will the MSIVs be affected by performing this procedure after the MSIVs are closed?

Response A RR Hll-P609 and RR H11-P611, MSIVs automatically open with no operator action.

MSlVs have no automatic open feature.

Response B Hll-P601 and Hll-P602, MSIVs automatically open after a 30 second time delay MSlVs have no automatic open feature Response C Hll-P601 and Hll-P602, MSIVs can be opened manually when the RPV level isolation signal is cleared.

The signal has to be cleared and reset Response D - Correct Answer RR Hll-P609 and RR Hll-P611, MSIVs can be manually opened after the isolation signal is reset.

Reference:

29.ESP.11 Author: BOLLINGER Keywords: ESP Not Archived Date Last Used:

Time: 0 Question ID: 34721 Points: I Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO 295037 2.4.34 3.8 3.6 SRO ESP

[7 STAC Part A

References:

[7 STAl 0 Part B 29.ESP.11 LOR [7 Open Ref.

0 NOC Close Ref.

IN0 Static

Question #19 Details EQ-OP-315-0166-000-B003-004 NRC RO Retake 2003 Question Text The plant is operating at 100% power when the following alarms occur:

3D32, Div I/II RB Vent Radn Monitor Upscale 3D36, Div I/II RB Vent Exh Radn Monitor Upscale Trip What actions must the CRNSO perform?

Response A - ' Correct Answer Verify Secondary Containment isolated and SGTS initiated.

Reference LP-OP-315-066,3036 Response B Direct a channel function test performed on all RB Vent Exhaust radiation monitors to verify readings.

Although surveys and samples woufd be directed, a "channel function test" is not performed.

Response C Declare the radiation monitors inoperable, notify Chemistry to take samples, and initiate a plant shutdown.

None of these alarms would indicate the rad monitors are inoperable.

Response D Perform an immediate plant shutdown due to loss of Secondary Containment integrity.

These are not indications of a loss of Secondary Containment.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34722 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO 295038 Al.06 3.5 3.6 SRO 0 ESP 0 STAC Part A

References:

STAl 0 Part B 3D36 LOR 0 Open Ref.

LP-OP-315-0166 0 NOC @Close Ref.

IN0 Static

Question #20 Details EQ-OP-802-0201-000-0001-001 NRC RO Retake 2003 Question Text The plant is operating at 96% with a fire in progress.

A plant shutdown and Control Room evacuation is REQUIRED when the fire is.. ...

Response A - Correct Answer in a zone that may cause spurious actuation of equipment.

Reference:

20.000.22,20.000.18bases Response B lasts longer than 15 minutes.

This is reportable, but doesnt REQUIRE shutdown and evacuation Response C affects fire fighting equipment.

If true, more help would be called from outside the plant.

Response D on the third floor of the Turbine Building.

Afthough there is direct access to the CR from the TB, its not REQUIRED.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34736 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO aILO 600000 A2.13 3.2 3.8 aSRO 0 ESP

References:

17 STAC PartA 20.000.22 0 STAl 0 Part B 20.000.18 bases 0 LOR Open Ref.

17NOC Close Ref.

IN0 Static

Question # 21 Details EQ-OP-315-0121-000-A008-001 NRC RO Retake 2003 Question Text The plant has experienced a loss of Feedwater (FW). High Pressure Coolant Injection (HPCI) has automatically started. Reactor Core Isolation Cooling (RCIC) started and tripped.

A short time later, HPCI trips on L8.

HPCI trips to prevent ...

Response A - Correct Answer turbine damage from carry-over Reference ST-UP-31 5-0021 Response B overspeed of the HPCI turbine Turbine woutd not be expected to go faster with water a s the moving medium.

Response C operations with insufficient water above the core Water level will be too high, not too low.

Response D operations with the steam separator skirts uncovered Water level will be too high, not too fow.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34723 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO aILO 295008 K3.05 3.5 3.6 aSRO ESP

References:

0 STAC 0 Part A ST-OP-315-0021 STAl 0 Part B 0 LOR Open Ref.

NOC Close Ref.

IN0 0 Static

Question #22 Details EQ-OP-315-0121-000-A008-002 NRC RO Retake 2003 Question Text What condition can lead to carryunder, and what is the potential impact of carryunder on the plant?

Response A - Correct Answer Low RPV level, cavitation of the recirculation pumps

Reference:

ST-OP-315-OOO7, ST-OP-I 74 Unit 8 page 13 Response B High RPV level, exceeding core thermal limits High RPV fevel would cause carryover, Core thermal firnits are threatened by loss of FW heating Response C High RPV level, damage to main turbine blading High RPV fevel would cause carryover Response D Low RPV level, neutron flux instabilities Low RPV level would cause carryunder, but the direct recult would be cavitation of the recirculation pumps.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 2 Question ID: 34737 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO a 110 295009 K1.01 2.7 2.9 SRO 0 ESP STAC Part A

References:

0 STAl Part 6 ST-OP-915-0007 LOR 0 Open Ref.

ST-OP-174 Unit 8 NOC aClose Ref.

IN0 0 Static Page: 1

Question #23 Details EQ-OP-315-0117-000-C001-001 NRC RO Retake 2003 Question Text The plant is operating at full power and the following conditions exist :

. 8D41 0 Div 1 DW Temp Hi Ann .................................. activates

. All DW Cooling Fans.................................................

T47-R803A, point 16..................................................

operating

> 155°F If the average drywell temperature has risen from 132°F to 135°F during the last 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, which one of the following actions is appropriate?

Response A - Correct Answer Increase GSW cooling to RBCCW per ARP 8D41.

Reference:

8D41,23.415 Response B Operate all available Drywell Cooling per 29.100.01.

TTatcnt entered thc EOPs, all DW cooling is already operating.

Response C Shift DW Cool Fans 1,2,3 and 4 to low speed per 23.415.

WouIcT c;iiise temperature to go up Response D Manually initiate EECW and EESW Systems per 20.127.01.

Not iii this procedure.

Author: BOLLINGER Keywords: CONTAINMENT Not Archived Date Last Used: 10/22/1999 GSW Time: 3 Question ID: 34724 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value a RO laILO 29501 2 Al.01 3.5 3.6 aSRO 17 ESP 17 STAC 0 PartA References 0 STAl Part B 8D41 0 LOR Open Ref.

23.415 0 NOC aClose Ref.

IN0 static

Question #24 Details EQ-OP-315-0105-000-A019-001 NRC RO Retake 2003 Question Text The plant was operating at 100% power.

Due to multiple instrument malfunctions, a MSIV isolation has occurred while operating at full power.

No operator action is taken, and all systems and automatic actions function as designed.

Which of the following indicates the expected range of reactor pressure 15 minutes after the MSIVs have closed?

Response A 50 to 150 psig This is expected pressure range after a depressurization, not MSIV kola tion.

Response B - Correct Answer 905 to 1017 psig

Reference:

ST-OP-315-0005,23.201 Response C 935 to 1047 psig This is the range of I; S V, expected to be in the range of A SRV.

Response D 944 to 960 psig Expected range if the XISIVs were open with pressure controlled by the bypass ~ a l v c s Author: BOLLINGER Keywords: Not Archived Date Last Used: 10/22/1999 Time: 0 Question ID: 34725 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO 295020 K2.01 3.6 3.7 aSRO ESP

References:

STAC 0Part A 23.201 0 STAl Part B ST-OP-315-0015 LOR Open Ref.

NOC Close Ref.

0IN0 0 Static

Question #25 Details EQ-OP-315-0139-000-C005-001 NRC RO Retake 2003 Question Text Preparations are in progress to start High Pressure Coolant Injection (HPCI) following maintenance activities. Torus water level is +1.5 inches. Which of the following applies?

Response A Raise Torus level to account for level drop when filling HPCI lines.

HPC1 lines already full, lower level to perform test, Response B Raise Toms level to account for swell during the the start of HPCI Starting HPCl doesnt cause swell in the Torus.

Response C Lower Torus level to prevent auto suction transfer when starting HPCI Starting HPCI wont cause an auto suction transfer.

Response D - Correct Answer Lower Torus level to prevent auto suction transfer when starting Torus cooling.

Reference:

23.202 Precaution 3.1 0 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 2 Question ID: 34738 Points: I Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO aILO 295029 K3.02 3.6 4.0 SRO ESP STAC 0 Part A 0 STAl Part 6

References:

[7 LOR Open Ref.

23.202 NOC Close Ref.

0IN0 Static

Question #26 Details EQ-OP-802-3005-000-0003-003 NRC RO Retake 2003 Question Text While the plant was operating at 100% power, the following plant conditions exist:

1D66, STEAM LEAK DETECTION AMBIENT TEMP HIGH...........on lD70, STEAM LEAK DETECTION DIFF TEMP HIGH......... ...........on A Group 8 isolation has also occurred.

Where is the leak coming from?

Response A - Correct Answer Reactor Core Isolation Cooling

Reference:

1D66,1070, ST-OP-315-0048 Response B Steam Tunnel Group 1 Isolation Response C High Pressure Coolant Injection Group 6 Isolation Response D Reactor Water Cleanup Group 10: 1 1 Isolation Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 34728 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO la ILO 295032 A2.03 3.8 4.0 la SRO ESP

References:

0 STAC PartA 1D66 STAl Part B 1070 0 LOR Open Ref.

ST-OP-315-0048 NOC Close Ref.

IN0 static

Question #27 Details EQ-0 P-802-3005-000-0001-017 NRC RO Retake 2003 Question Text The following conditions exist:

Reactor Power ...................... 96% and stable.

Control Room Pressure.........+- 0.075H20 and stable.

Reactor Building Pressure......-0.20H20 and stable.

Turbine Building Pressure.......-0.10 H2O and stable.

Which one of the following actions is required?

Response A Enter 20.413.01, Control Center HVAC System Failure.

No entry condition for 20.413.01 Response B Enter 29.100.01, Secondary Containment and Radioactive Release.

No entry condition for EOPs Response C Enter ARP 8D13, Turbine BLDG Press High.

Turbine Bldg pressure is in acceptable range.

Response D - Correct Answer Enter ARP 8D10, MCR Building Pressure HigNLow .

Reference:

807 0 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 2 Question ID: 34730 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 295035 A2.01 3.8 3.9 SRO 0 ESP

References:

STAG 0 PartA 8D10 STAl 0 Part 6 LOR Open Ref.

NOC nClose Ref.

0IN0 0 Static

Question #28 Details EQ-OP-315-0141-000-A021-004 NRC RO Retake 2003 Question Text Reactor pressure is 900 psig and RHR Loop B is running in response to a valid LPCI initiation signal.

Which statement describes the expected flow indication on the Division I1 RHR System Flow Recorder?

Response A - Correct Answer 0 gpm

Reference:

ST-OP-315-0041, ST-OP-315-OO41 Response B 3000 gpm Doesn't sense flow through the min flow valve.

Response C 10,000 gpm Reasonable flow but RPV prcssurc is greater than IPCI shutoff head.

Response D 20,000 gpm Rcasonablc flow b ~ t RPV t pressure is greater than LPCl shutoff head.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34739 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO 203000 A I .02 3.9 4.0 aSRO ESP

References:

STAC PartA ST-OP-315-0041 STAl Part B LOR Open Ref.

NOC aClose Ref.

C3 IN0 0 Static

Question #29 Details EQ-OP-315-0141-000-A014-004 NRC RO Retake 2003 Question Text The plant is in a refueling outage. Residual Heat Removal (RHR) is aligned for Shutdown Cooling using RHR pump B.

What is the power supply to RHR pump B?

Response A Bus 64 A BOP 4 160V bus Response B Bus 64 B RIlR pump A Response C - Correct Answer Bus 65 E

Reference:

ST-OP-315-0041 Response D Bus 65 F RHR pump D Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34740 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 205000 K2.01 3.1 3.1 SRO ESP

References:

STAC 0 Part A ST-OP-315-0041 0 STAl Part B LOR c]Open Ref.

NOC Close Ref.

[51 I N 0 Static

Question #30 Details EQ-OP-315-0141-000-A012-001 NRC RO Retake 2003 Question Text Division I Residual Heat Removal (RHR) System is operating in the Shutdown Cooling Mode with RHR Pump C running.

Post Maintenance Testing requires that E l 150-F004C, Division I RHR Pump C Torus Suction Isolation Valve be to manually stroked open and closed.

What is the consequence of operating this valve?

Response A Violation of brittle fracture temperature limits due to cold water being pumped from the Torus to the Reactor Pressure Vessel.

Brittle fracture ;I concern when the KPV is pressurized.

Response B - Correct Answer Lowering RPV level by establishing a drain path from the Reactor Pressure Vessel to the Torus.

Reference:

ST-OP-315-O041,23.205 Step 3.2.8 Response C Overflow of the Reactor Well and Fuel Pool due to Torus water being pumped into them.

Wctuld actually cause water level to go down.

Response D Severe water hammer due to improper fill and vent.

I-ines arc atrc-e;idyfilled and ventcd.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34741 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO a ILO 205000 K5.02 2.8 2.9 aSRO ESP

References:

0 STAC Part A ST-OP-315-0041 0.STAI 0.Part 3 23.205 LOR Open Ref.

NOC Close Ref.

I7 I N 0 I7static

Question #31 Details EQ-OP-315-0139-000-B007-004 NRC RO Retake 2003 Question Text The plant has experienced a Station Blackout. High Pressure Coolant Injection (HPCI) has started automatically and is supplying the Reactor Pressure Vessel (RPV).

What is the HPCI response to Automatic Depressurization System blowdown?

Response A HPCI isolates to prevent pump cavitation.

Steam supply pressure doesn't aflect cavitation.

Response B The Minimum Flow Valve opens to maintain the set flowrate.

Opening the valve would cause indicated flow to dccrease Response C The Suction Valves switch to the Condensate Storage Tank to prevent pump cavitation.

Suction valves normally switch froIn the CS'I' to the Torus Response D - Correct Answer The Turbine Control Valve opens to maintain the set flowrate.

Reference:

ST-OP-315-OOJSl Author: BOLLINGER Keywords: HPCI Not Archived Date Last Used: DC ELEC Time: 2 Question ID: 34742 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 206000 K6.08 3.8 3.8 SRO ESP

References:

STAC Part A ST-OP-915-0039 0 STAl Part B LOR Open Ref.

0 NOC Close Ref.

0 IN0 0 Static

Question #32 Details EQ-OP-315-0140-000-A021-001 NRC RO Retake 2003 Question Text The Core Spray System is lined up in the Normal Standby Mode when a plant transient occurs.

Drywell Pressure ......................................... 13 9 psig.

Reactor Pressure ......................................... 210 psig.

All systems are operating normally.

What is the status of the Core Spray System?

Response A - Correct Answer Core Spray Pumps are running E21-FO05A5 CSS Loop A B Inboard Is0 Valves are OPEN FOOGA/B CSS Loop A/B Inboard Check Valve OPEN

Reference:

ST-OP-315-0O4Oy23.203 Section 5.3 Response B Core Spray Pumps are running E21-F005A/B CSS Loop A B Inboard Is0 Valves are OPEN FOOGA/B CSS Loop A/B Inboard Check Valve CLOSED Below the injection pr-cssurc, should have flow wid1 chcck valves open Response C Core Spray Pumps are running E21-F005A/B CSS Loop A/B Inboard Is0 Valves are CLOSED FOOGA/B CSS Loop A/B Inboard Check Valve OPEN Below tlie injection ~I'CSSUI'C, should have flow wit17 check valves open.

Response D Core Spray Pumps are not running E21-FO05AB CSS Loop A/B Inboard Is0 Valves are CLOSED FOOGA/B CSS Loop A/B Inboard Check Valve CLOSED Below the in-jection pressure, should have flow with check valves open.

Author: BOLLINGER Keywords: Not Archived Date Last Used: 2/13/2002 Time: 2 Question ID: 34743 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 209001 2.4.2 3.9 4.1 aSRO ESP

References:

0 STAC Part A ST-OP-315-0040 STAl I7 Part B 23.203 c]LOR Open Ref.

0 NOC aClose Ref.

0 IN0 static

Question #33 Details EQ-0P-315-0140-000-A021-002 NRC RO Retake 2003 Question Text The plant was operating at 100% when there was a simultaneous Loss of Offsite Power and a Loss Of Coolant Accident.

How are the Core Spray system pumps affected?

Response A All pumps start on a Reactor Pressure Vessel Level 2 signal.

Pumps start on Level 1 or high DU7pressure.

Response B All pumps must be manually started after the Emergency Diesel Generators (EDG) energize the ESF buses.

Piimps start automaticalIy ;tfler ESF busses energize on Level I or high DW pressure.

Response C - Correct Answer All pumps start 5 seconds after the EDGs energize the ESF buses.

Reference:

ST-OP-315-0040 Response D Division I pumps start when CTG 11- 1 energizes the Division I ESF buses.

Division I1 pumps start after the Division I1 EDGs energize the Division I1 ESF buses.

Half right - Div 1 piinips sturt after Div 1 EDGS energize the Div 1 ESF busses.

Author: BOLLINGER Keywords: CSS Not Archived Date Last Used: LOCA Time: 0 Question ID: 34744 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 209001 A3.02 3.8 3.7 SRO ESP

References:

STAC 0 Part A ST-OP-315-0040 STAl 0 Part 6 0 LOR 0 Open Ref.

NOC Close Ref.

IN0 0 Static

Question #34 Details EQ-OP-315-0114-000-C010-002 NRC RO Retake 2003 Question Text On direction from the CRS,an operator has placed the SLC Initiation Keylock Switch (C4100-M004) in the PMP A Run position.

The following indications are noted 30 seconds later:

C41 LIR601 (SLC Tank Level) steady Primer circuit continuity indicators OFF SLC pump A red light ON, green light OFF C41 PI R600 (SLC Pump Discharge Pressure) pulsating at 1400 psig These are indications of what condition, and what should the operator do?

Response A Normal operation for the SLC System; monitor SLC Tank level.

Not normal indication -1evc1, pressure not right.

Response B - Correct Answer C41-F004A, Pump A Squib Valve, failed to fire; start SLC pump B.

Reference:

23.139 Step 5.3.2 Response C C41-F001, SLC Storage Tank Outlet Valve, is open; dispatch operator to close C41-FO01.

This is normal limup.

Response D C41-F029A, SLC Pump A Discharge Relief Valve, failed open; dispatch operator to gag open C4 1-F029A.

This woulcl indicate a lower pump dischargc pressure.

Author: BOLLINGER Keywords: SLC Not Archived Date Last Used:

Time: 3 Question ID: 34745 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO 21 1000 A202 3.6 3.9 0 SRO ESP

References:

0 STAC PartA 23.139 0 STAl Part B LOR Open Ref.

NOC a Close Ref.

IN0 0 static

Question #35 Details EQ-OP-315-0127-000-A018-003 NRC RO Retake 2003 Question Text The plant is operating at 96%. The Reactor Vessel Steam Dome Pressure - High Trip Unit (B21-N678) for Channel A2 has failed high.

How will this failure affect the plant?

Response A No affect Satisfies logic for half scram in A.

Response B Full Scram The RPS logic is 1 out of 2 twice, n o t satisfied in this case.

Response C - Correct Answer Half Scram A

Reference:

ST-OP-31!j-OOZ7,23.603 Page IO Response D Half Scram B The RPS logic is I out of 2 twicc, satisficd for A trip string, not 13.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34747 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 2 12000 K1.02 3.7 3.9 SRO 0 ESP

References:

0 STAG Part A ST-OP-315-0027 STAl Part B 23.601 LOR Open Ref.

NOC Close Ref.

0 IN0 0 Static

Exam Bank Question #36 Details EQ-OP-315-0123-000-A015-001 NRC RO Retake 2003 Question Text During a reactor start-up with all IRMs on Range 5 , IRM A failed high. IRM A is then bypassed using the Bypass Switch.

IRM A has caused a..

Response A full scram and rod block due to a Upscale Trip Will not cause a full S C T : ~

Response B - Correct Answer half scram and rod block due to a Upscale Trip

Reference:

ST-OF-315-0023,ST-UP-3f 5-0023 Response C full scram and rod block when placed in Bypass Will not cause a full scrani;

Response

half scram and rod block when placed in Bypass The half scram and rod block was caused before being placed in bypass, Bypass could be confuscd with Modc switch in Stlrndby Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34748 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO la ILO 215003 K3.01 3.9 4.0 aSRO c]ESP

References:

STAC 0 PartA ST-OP-315-0023 0 STAl 0Part B LOR 0 Open Ref.

NOC aClose Ref.

IN0 0 Static

Question #37 Details EQ-OP-315-0122-000-A017-002 NRC RO Retake 2003 Question Text A plant startup is in progress. The SRM Retract Permit Light is on. The Reactor Operator attempts to retract Source Range Monitor (SRM) A, but the detector does not move.

The SRM detector will not move because the ....

Response A Intermediate Range Monitor range switch is in the wrong position IRAMrange determines when the SKM Retract Peimit light coines on, b u t doesn't prevent the SRM from being moved.

Response B - Correct Answer drive in signal is sealed in

Reference:

ST-OW315-0022 Response C SRM detector is not in the full in position Detector not full in doesn't prevcnt outward movcmcnt.

Response D SRM counts are less than 100 CPS SRM counts are an administrative limit, not an interlock for movement.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34749 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 21 5004 K4.04 2.8 2.9 SRO ESP

References:

0 STAC 0 Part A ST-OP-315-0022 STAl 0 Part B 0 LOR 0 Open Ref.

NOC Close Ref.

IN0 Static

Question #38 Details EQ-OP-315-0122-000-A017-003 NRC RO Retake 2003 Question Text A plant startup is in progress.

Source Range Monitor A downscale rod blocks are bypassed when Intermediate Range Monitor Channel(s). . ..

Response A A is on range 1.

SRM A, C art: ganged with IRM A,C,E,G on Range 3 Response B A, C are on range 1.

SRM A, C art' ganged with IRiM A.C,E,G on Range 3 Response C A, C are on range 3.

SRM A, C x e ganged with IRNl A,C,E,G on Range 3 Response D - Correct Answer A, C, E, G are on range 3.

Reference:

ST-OP-315-0022 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34750 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO lzlILO 21 5004 A3.04 3.6 3.6 SRO 0ESP

References:

0 STAC 0 Part A ST-OP-315-0022 0 STAl 0Part B 0LOR [7 Open Ref.

NOC Close Ref.

IN0 0Static

Question #39 Details EQ-OP-315-0024-000-A011-001 NRC RO Retake 2003 Question Text What portion of the Power Range Neutron Monitoring (PRNM) System generates a safety trip signal and alarm if the Simulated Thermal Power (STP) signal value exceeds the Flow-Biased upscale setpoint?

Response A Local Power Range Monitor detectors Detectors don't generate trip signals Response B 2 of 4 Logic Modules Don't generate an alarm signal Response C Recirculation Flow Monitors Monitors don't generate trip signals Response D - Correct Answer Average Power Range Monitor channels

Reference:

ST OF"-315-0024 Author: BOLLINGER Keywords: PRNM Not Archived Date Last Used:

Time: 2 Question ID: 34751 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO rn ILO 215005 K4.07 3.7 3.7 SRO ESP 0 STAC Part A

References:

STAl Part B ST OP-315-0024 LOR Open Ref.

[7 NOC Close Ref.

IN0 0 Static Page: 1

Question #40 Details EQ-OP-315-0143-000-A014-001 NRC RO Retake 2003 Question Text Motor Control Center (MCC) 2PA-1 has been removed from service. Which component is affected by the loss of MCC 2PA- 1?

Response A A Recirc MG emergency oil pump BOP DC Response B South Reactor Feed Pump emergency oil pump BOP DC Response C - Correct Answer Reactor Core Isolation Cooling (RCIC) Barometric Condenser Vacuum pump

Reference:

ST-OP-315-0043 Response D High Pressure Coolant Injection (HPC1)Barometric Condenser Vacuum pump 2PB- 1 vs. 2PA- 1 Author: BOLLINGER Keywords: RCIC Not Archived Date Last Used:

Time: 1 Question ID: 34752 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO aILO 217000 K2.04 2.6 2.6 @ SRO ESP STAC Part A

References:

STAl Part B Si-OP-315-0043 c]LOR Open Ref.

17 NOC [3Close Ref.

c]I N 0 Static

Question #41 Details EQ-OP-315-0142-000-A012-001 NRC RO Retake 2003 Question Text The Control Room is performing 24.137.1 1, Safety Relief Valve (SRV) Operability Test. The test has progressed to testing B2104-F013P, Main Steam Line D SRV.

After B2 104-FO13P is cycled for the test, annunciator ID6 1, SRV Open, remains on.

What is the cause for this alarm?

Response A B2104-FO13P is open Annunciator status is determined by tailpipe temperature, not actual salve position Response B B2104-FO13P close contacts failed There are no closc contacts for the SRVs Response C - Correct Answer B2104-FO13P tail pipe temperature is 225'F

Reference:

ST-OP-315-0042 Response D B2104-FO13P tail pipe pressure is 20 psig Tail pipe prcssurc of 30 psig gives the alarm Author: BOLLINGER Keywords: ADS Not Archived Date Last Used:

Time: 0 Question ID: 34753 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 21aooo Al.01 3.4 3.6 aSRO ESP

References:

STAC 0 Part A ST-OP-815-0042 STAl Part B 0 LOR 0 Open Ref.

NOC aClose Ref.

0 IN0 0 Static

Question #42 Details EQ-OP-315-Ol27-OOO-AOl8-OO4 NRC RO Retake 2003 Question Text The plant is operating at 85% power when the following occurs:

RPS MG set 'A'trips Various alarms indicate in the Control Room All other systems function as designed Which of the following would be an expected alarm?

Response A 10D71 Div I1 120V RPS Bus 1B Power Failure.

This a Div I RPS failurc Response B 3D74 Trip Actuators B 1 B 2 Tripped This a Div I RPS failurc, Trip actuator A ll-42 would be tripped.

Response C 2D36 NSSSS Isolation CH B/D Division 2 alarm. Div I is lost.

Response D - Correct Answer 1D39 NSSSS Isolation CH AX.

Reference:

ST-OF-315-0027 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 2 Question ID: 34754 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 223002 2.4.46 3.5 3.6 aSRO ESP

References:

STAC Part A ST-OP-315-0027 STAl Part B 23.316 LOR Open Ref.

NOC @Close Ref.

IN0 static

Question #43 Details EQ-OP-315-0198-000-0005-004 NRC RO Retake 2003 Question Text How will a loss of Reactor Building Closed Cooling Water affect the Primary Containment Isolation System (PCIS)?

PCIS will.. .

Response A shut down Steam Tunnel Cooling on High Steam Tunnel Temperature.

Nothing shuts down Steam Tunnel Cooling Response B isolate the Steam Tunnel area on High Steam Tunnel Temperature.

N o isolation of Steam Tiinnel area Response C scram the Reactor on High Steam Tunnel Temperature.

MSIVs close, which woiild cause a scram. biit therc is 110 scram on high Sicain T W I I I ~ I Temnperature Response D - Correct Answer isolate the Main Steam Lines on High Steam Tunnel Temperature,

Reference:

SX-OP-315-0O98 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34755 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO aILO 223002 K1.19 2.7 2.9 aSRO ESP

References:

STAC Part A ST-OP-315-0098 STAl 0Part B 0 LOR 0 Open Ref.

0 NOC a Close Ref.

0 IN0 0 static

Question #44 Details EQ-OP-315-0105-000-0206-001 NRC RO Retake 2003 Question Text The reactor was operating at 100% power, when an automatic scram signal occurred and the following plant conditions exist :

ATWS, reactor power..................................................................... 12 %

Control Rods.. ...................alternate rod insertion activities unsuccessful Reactor pressure ......................................................... 940 psig and stable RPV water level ................................................................... + 115 inches MSIVs.................................................................................. failed closed Torus temperature ................................................. 95'F (rising 4'F/min)

Drywell temperature ..................................................................... .125 F Drywell pressure .......................................................................... 1.1 psig RHR System.................................................. both loops in Torus Cooling SLC Pumps.. ............................................................................ inoperable Alternate Boron Injection ..................being aligned by the Operating Crew Given the above conditions, how many Safety Relief Valves are open?

Response A 1

Would only pass about 6% steam flow, pressure would bc rising Response B . - Correct Answer 2

Reference:

ST-UP-315-0005,ST-OP-315-0005 Response C 4

At this pressure, only Lo-Lo set valves tvotild be open, with 4 open. pressure would bc lowering.

Response D 5

At this pressure, only Lo-Lo set valvcs would bc open, with 4 open: prcssurc would bc locvering.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

lime: 4 Question ID: 34756 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO aILO 239002 K5.01 3.4 3.5 SRO ESP

References:

0 STAC 0 PartA ST-OP-315-0005 STAl 0 Part B LOR Open Ref.

0 NOC Close Ref.

IN0 Static

Question #45 Details EQ-OP-315-0107-000-0006-007 NRC RO Retake 2003 Question Text A Reactor Startup is in progress. Reactor Power is currently 20%. RPV level control is currently on the Start Up Level Control Valve. At what point, and why, is Feedwater Control transferred to Single element control?

Response A At 25% power so that the Main Turbine Generator can be synchronized to the offsite grid without violating Thermal Limits.

Main tienerator is synchronized earlier in startup.

Response B When feedwater temperature is within 5°F of RPV temperature to prevent power transients in the Reactor.

Feedwater temperature is never within 5°F of RPV tcmperr-lturc when the Mode switch is in run.

Response C Prior to placing a second Condenser pump in service due to the condensate minimum flow setting of 9000 gpm.

The second Condenser pump is placed in service prior to starting a licater feed pump.

Response D - Correct Answer When RFP suction flow is greater than 25% to prevent oscillations of the Reactor Feed Pump Minimum Flow Valve and Reactor Water Level.

Reference:

23.107 Step 3.1.4 Author: BOLLINGER Keywords: RX FEEDWATER Not Archived Date Last Used:

Time: 0 Question ID: 34757 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO 259002 A4.06 3.1 3.2 SRO ESP 0 STAC Part A

References:

STAl 0 Part B 23.107 LOR 17Open Ref.

NOC aClose Ref.

[7 I N 0 Static

Question #46 Details EQ-OP-315-0120-000-B007-003 NRC RO Retake 2003 Question Text The plant is operating at 100% power steady state conditions when the following alarms are received:

9D70 Div 1 120V RPS Bus 1A Power Failure 3D73 Trip Actuators A1/A2 Tripped 3D75 Reactor Vessel High Press Channel Trip 3D79 Reac Vessel Water Level L3 Channel Trip 3D85 Primary Containment High Press Channel Trip.

Based on these alarms, which of the following would the operator expect?

Response A MSIVs are shut There will only be a half isolation sigrial Response B - Correct Answer Div 1 SGTS is running

Reference:

ST-OP-315-0020,23.316 Enclosure A, Page 2 of 6 Response C Full scram There will only be a half scram.

Response D Div 2 Control Air Compressor is running Div 1 CAG auto starts on Div 1 RPS loss.

Author: BOLLINGER Keywords: RPS Not Archived Date Last Used:

Time: 2 Question ID: 34782 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO ElILO 261000 K6.05 3.1 3.2 aSRO ESP STAC 0 Part A

References:

STAl Part B ST-OP-315-0020 17LOR Open Ref.

NOC Close Ref.

0 IN0 Static

Question #47 Details EQ-OP-315-0165-000-A021-003 NRC RO Retake 2003 Question Text The following conditions exist:

Reactor power ......................................... 98%

Drywell Pressure..................................... 1.1 psig, raising slowly Reactor water level.................................. 185 inches, lowering slowly All other systems are functioning as designed.

If the pressure and level trends continue, what can the operator expect to happen to the Emergency Diesel Generators (EDG), and what action should be taken?

Response A EDG will auto start, EDG output breaker will close, and loads will be sequenced onto the EDG.

Dispatch operator to verify proper operation of the EDG.

Loads wont sequence without n loss of power Response 0 EDG will not auto start.

Dispatch operator to start the EDG.

EDG will auto start.

Response C - Correct Answer EDG will auto start.

Run the EDG loaded for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before stopping.

Reference:

ST-OP-315-0065, 23.307 Response D EDG auto starts, load sequencer strips loads.

Dispatch operator to verify proper operation of the EDG.

Loads wont sequencc without a loss of power Author: BOLLINGER Keywords: EDG Not Archived Date Last Used:

Time: 0 Question ID: 34766 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO aILO 262001 A2.02 3.6 3.9 SRO ESP

References:

STAC Part A ST-OP-315-0065 STAl 0 Part B 23.307 0 LOR 0 Open Ref.

NOC Close Ref.

IN0 Static

Question #48 Details EQ-OP-315-0162-000-A001-001 NRC RO Retake 2003 Question Text With the plant operating at full power, several alarms, including annunciator 3D22 (UPS UNIT A/B TROUBLE), are received. The following conditions exist:

UPS Bus A Rectifier DC Output ............................... 0 amps UPS Bus B Sync Monitor light ................................. ON Bright UPS Bus A Inverter AC Output Light ......................... ON UPS Bus B Inverter AC Output Light ......................... ON 0 Bypass to Alternate Line Switch (Units A and B).......NORMAL Which of the following caused annunciator 3D22 to activate?

Response A Unit B Static Transfer Switch Failure.

Unit I3 is not afftcled Response B Unit B Test Switch has been placed in "ALT LINE".

Unit R is not affcctcd Response C Loss of bus 72R.

7% affects E3 rectifier Response D - Correct Answer Loss of bus 72M.

Reference:

ST-OP-315-0062 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34758 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO la ILO 262002 K4.01 3.1 3.4 aSRO 0 ESP STAG [7 Part A

References:

[7 STAl Part B ST-OP-315-0062 LOR Open Ref.

0 NOC [3 Close Ref.

nI N 0 0 static

Question #49 Details EQ-OP-315-0164-000-C002-002 NRC RO Retake 2003 Question Text A reactor startup is in progress with the mode switch in START-UP. Due to a malfunction, the 24/48 V Division 1 bus is de-energized. What is the plant response to this event?

Response A - Correct Answer Half scram, rod block

Reference:

ST-OP-315-0023, ST-UP-315-0023 Response B Full scram, rod block Only Div 1 affected. catises half scrani.

Response C Full scram, no rod block Only Div I affected, causes hiilf scram.

Response D Rod block, no half or full scram Only Div 1 affccted. causes half scriini.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34791 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 263000 K3.03 3.4 3.8 aSRO ESP

References:

STAC 0 Part A STAl 0 Part B ST-OP-315-0023 0 LOR 0 Open Ref.

NOC Close Ref.

IN0 Static

Question #50 Details EQ-OP-315-0165-000-A016-001 NRC RO Retake 2003 Question Text The plant experienced a loss of Bus 64B.

The bus was subsequently restored to the normal lineup EXCEPT the operators neglected to reset the digital load sequencer.

Following the restoration, all power is again lost to Bus 64B.

How will the EDG and electrical distribution system respond to this event?

Response A The EDG will require a manual start. The loads on bus 64B will sequence after the output breaker is closed.

EDG auto starts 011 a Lost; of poer Response B The EDG will require a manual start. The loads on bus 64B will NOT sequence after the output breaker is closed.

EDG auto starts on a loss of power Response C - Correct Answer The EDG will automatically start. The loads on bus 64B will sequence after the output breaker is closed.

Reference:

ST-OP-3I5-QOS5 Response D The EDG will automatically start. The loads on bus 64B will NOT sequence after the output breaker is closed.

Anytime thc output brcakcr closes, and thc sequexiccr has not bcen reset, thc loads will sequeiicc on, Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34760 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO n110 264000 K5.06 3.4 3.5 SRO ESP

References:

STAC Part A ST-OP-315-0065 0 STAl Part B 17LOR Open Ref.

0 NOC aClose Ref.

0IN0 0 Static

Question #51 Details EQ-OP-802-2001-000-R001-005 NRC RO Retake 2003 Question Text The plant has experienced a seismic event. A small steam leak in the drywell and loss of offsite power have occurred. The following conditions exist:

Drywell pressure........................................................... 5 psig Drywell temperature.................................................... .150"F RHR pumps A, B, D ..................................................... running CS pumps A, B, D ........................................................ .nning Breaker C8, 4160 X-TIE to Bus 12EB........................ closed Breaker C6,4 160 Normal Feed To Bus 64C.. ...........open What is the status of the Emergency Diesel Generators (EDG), and what action should be taken?

Response A EDG 12 is running but not loaded due to bus lockout, Perform actions of 20.300.64C, Loss of Bus 64C There is no 1x1s lockout bccausc C6 is closed Response 6 - Correct Answer EDG 12 failed to start, perform actions of 20.307.01, Emergency Diesel Generator Failure.

Reference:

20.307.01 Response C EDG 13 is running but not loaded due to bus lockout, Perform actions of 20.300.65E, Loss of Bus 65E 1333 is ruiining and loaded Response D EDG 13 failed to start, perform actions of 20.307.01, Emergency Diesel Generator Failure.

EDG is running and loaded Author: BOLL1NG ER Keywords: EDG Not Archived Date Last Used: 41 60/480VELEC Time: 0 Question ID: 34792 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO I3ILO 264000 A2.10 3.9 4.2 SRO 0 ESP

References:

STAC 0 Part A 23.307.01 0 STAl Part B 0 LOR 0 Open Ref.

0 NOC a Close Ref.

0 IN0 Static

Question #52 Details EQ-OP-802-2001-000-R006-003 NRC RO Retake 2003 Question Text The plant was operating at 85% power when a progressive loss of IAS occurred. The CRS directed the mode switch placed in shutdown.

Which of the following was the reason the CRS directed shutdown of the plant?

Response A - Correct Answer Scram Air Header Pressure Low

Reference:

20.129.01 Response B The SULCV failed open This will evelltuiilly happen. but we re not feeding with StrL,CV Response C The SRVs failed open.

?r/TSIVsmay bc affectcct, not SRVs.

Response D Condensate Filter Demin Bypass Valve failed open This might happen, but is not the reason for a scram.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34761 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 300000 K3.02 3.3 3.4 aSRO 0 ESP

References:

STAG Part A 20.129.01 0 STAl Part B LOR Open Ref.

NOC Close Ref.

IN0 0 Static

Question #53 Details EQ-OP-3I5-0167-000-B007-002 NRC RO Retake 2003 Question Text Reactor Power is raised from 25% to 75%.

Which of the following describes the response of the RBCCWEECW system?

Response A The RBCCW differential pressure control valve opens.

More load on system, valve will close.

Response B - Correct Answer The RBCCW differential pressure control valve closes.

Reference:

ST-OP-315-0067 Response C The RBCCW temperature control valve closes.

More load on system, valve will open.

Response D The EECW temperature control valve opens.

EECW shut down in this condition.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34763 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 400000 A I .03 2.7 2.7 SRO 0 ESP

References:

STAC Part A ST-OP-315-0067 STAl Part B 0 LOR 0 Open Ref.

0 NOC Close Ref.

IN0 static

Question #54 Details EQ-OP-315-0110-000-B002-002 NRC RO Retake 2003 Question Text Fill in the blanks The Rod Movement Control Switch is taken to "IN."

-(a)- Directional Control Valves -(b)-, and the below piston area of the Drive Piston is

-(c>-

Response A (a>4 (b) deenergize (c) vented There arc 4 Directional Control Vals-cs. b ~ only t 2. arc energized at a time.

Response B (a>4 (b) energize (c) pressurized

'There are 4 Directional Conlrol Valves, but only 2 are eiiergizect al a time.

Response C (a) 2 (b) deenergize (c) vented There arc 4 Directional Control Valves, but only 2 arc energized ai a timnc.

Response D - Correct Answer (a) 2 (b) energize (c) pressurized

Reference:

ST-OP-315-0010 Author: BOLLINGER Keywords: CRDH Not Archived Date Last Used:

Time: 0 Question ID: 34764 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 201 002 K1.01 3.2 3.2 SRO 0 ESP

References:

STAC 0 Part A ST-OP-315-0010 STAl 0 Part B LOR Open Ref.

NOC Close Ref.

IN0 0 static

Question #55 Details EQ-OP-315-0111-000-A013-001 NRC RO Retake 2003 Question Text A reactor startup is in progress with the following conditions:

Rod Select Power Switch ........................................ ON Select button for rod 26-3 1..................................... ON 3D80, Control Rod Drift .......................................... ON What is the cause of the Control Rod Drift Alarm?

Response A - Correct Answer Rod 26-31 at position 35 with the Rod Control Movement Switch in OFF

Reference:

ST-OPS I 5-0 I 1 Response B Rod 26-3 1 at position 35 with the Rod Control Movement Switch in OUT NOTCH Rod Drift Alarm is caused by no drive signal, an odd recd switch pickcd up arid or an even reed switch not picked up.

Response C Rod 26-3 1 at position 34 with the Rod Control Movement Switch in OFF Rod Drift Alarm is caused by no drive signal, an odd reed switch picked up and or an even reed switch no2 picked up.

Response D Rod 26-31 at position 34 with the Rod Control Movement Switch in OUT NOTCH Rod Drift Alarm is caused by no drive signal, an odd reed switch picked up and or an even reed switch not picked up.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34765 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 214000 A3.02 3.2 3.1 aSRO 0 ESP

References:

STAC Part A ST-OP-315-011 c]STAl c]Part B LOR 0 Open Ref.

NOC aClose Ref.

c]I N 0 c]Static

Question #56 Details EQ-0P-802-3002-000-0004-017 NRC RO Retake 2003 Question Text The ambient temperature near a Reactor Pressure Vessel (RPV) level instrument has exceeded the RPV saturation temperature.

Which of the following describes the effect on RPV indicated level?

Response A Boiling in the reference leg increases the sensed differential pressure which results in indicated level decreasing.

Fundamcntals qucstion Response B Boiling in the variable leg decreases the sensed differential pressure which results in indicated level decreasing.

Fundameritals question Response C - Correct Answer Boiling in the reference leg decreases the sensed differential pressure which results in indicated level increasing.

Reference:

ST-OP-802-3002 Response D Boiling in the variable leg increases the sensed differential pressure which results in indicated level increasing.

Fundamentals question Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34767 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 216000 K3.24 3.9 4.1 aSRQ ESP

References:

STAC 0 Part A ST-QP-802-3002 STAi 0 Part B c]LOR Open Ref.

c]NQC Close Ref.

0 IN0 0 Static

Question #57 Details EQ-OP-315-0149-000-A011-001 NRC RO Retake 2003 Question Text With regard to the Primary Containment Monitoring System, what is the preferred alignment of the H202 monitoring subsystem sampling points and why is this alignment preferred?

Response A Alignment of either Div I or Div I1 H202 monitoring subsystem sampling points to the Drywell or the Torus is equally acceptable. Operation of PCRMS is not affected by the sampling point selection.

Rad monitoring is only in Divl and it needs to be aligned to the drywell to be operable.

Response B Alignment of either Div I or Div I1 H202 monitoring subsystem to either the Drywell or the Torus is equally acceptable. PCRMS is not required to be in operation when Ho monitoring is in service.

PCRMS is required to be operable.

Response C - Correct Answer Div I HzOz monitoring subsystem aligned to the Drywell and Div I1 H202 monitoring subsystem aligned to the Torus. This ensures PCRMS will meet its intended function.

Reference:

ST-OP-315-0049, 23.408 Response D Div I1 H202 monitoring subsystem aligned to the Drywell and Div I H202 monitoring subsystem aligned to the Torus. This ensures PCRMS will meet its intended function.

Rad monitoring is only in Divl and it necds IO bc aligned to thc drywell to be operable.

Author: BARRETT Keywords: CONTAINMENT MON SYS Not Archived Date Last Used:

Time: 0 Question ID: 34794 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 223001 A4.04 3.5 3.6 SRO 0 ESP

References:

STAC Part A ST-OP-315-0049 0 STAl [7 Part B 23.408 0 LOR 0 Open Ref.

NOC Close Ref.

[7 I N 0 Static

Question #58 Details EQ-OP-315-0141-000-A021-005 NRC RO Retake 2003 Question Text The plant has experienced a LOCA and RHR started in the LPCI mode.

Which of the following describes the operation of the RHR pump Minimum Flow Valve?

The Minimum Flow Valve .....

Response A opens when loop flow exceeds 3000 gpm Actually closes on increasing flow.

Response B opens when loop flow exceeds 5000 gpm Actually closcs on increasing flow.

Response C - Correct Answer closes when loop flow exceeds 3000 gpm

Reference:

ST-OP-315-0041 Response D closes when loop flow exceeds 5000 gpm Fully closed at 3000 gpni Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34768 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO [3 ILO 226001 K4.05 2.5 2.5 [3 SRO ESP

References:

STAG Part A ST-OP-315-0041 STAl c]Part B c]LOR 0 Open Ref.

NOC [3 Close Ref.

IN0 0 Static

Question #59 Details EQ-0 P-802-2002-000-00 14-003 NRC RO Retake 2003 Question Text The following conditions exist:

Reactor power.. ................................................. .85%

RPV pressure. ................................................... ..950 psig lowering In service pressure regulator................................. failed high The operator has performed the following:

Placed the mode switch in shutdown.

Tripped the Main Turbine.

Unsuccessfully attempted to close the Turbine Bypass Valves.

What is the effect on the plant?

Response A MSIVs close on excessive flow, pressure then stabilizes.

Cant get excessive flow through the bypass valves.

Response B Turbine control valves throttle open, pressure continues to decrease.

Turbine is tripped, thcse valves arc closed.

Response C MSNs close on lowering pressure, pressure then stabilizes.

h40dc switch in shutdown rernovcs the MS IV closure on low pressurc Response D - Correct Answer RPV pressure decreases, cooldown limit is exceeded.

Reference:

20.109.02 bases Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34769 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO la ILO 241000 K6.10 3.6 3.7 aSRO ESP

References:

0 STAC 0 Part A 20.109.02 bases 0 STAl 0 Part B LOR 0 Open Ref.

NOC aClose Ref.

IN0 Static

Question #60 Details EQ-OP-315-0107-000-B007-001 NRC RO Retake 2003 Question Text With the reactor operating at rated power, a reduction in the Reactor Feed Pump Suction pressure was observed.

Which of the following is the cause for this lowering of suction pressure?

Response A Inadvertent initiation of High Pressure Coolant Injection Causes feed pump suction pressure to increase.

Response B N22-F415 Heater Drain Pump N disch line LCV failed open Causes fced pump suction pressure to increasc.

Response C Standby Feedwater was started Causes feed pump suction pressure to increase.

Response D - Correct Answer Heater Drain Pumps tripped

Reference:

ST-OP-315-0031 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34784 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO a110 259001 A4.03 2.9 3.0 SRO 0 ESP

References:

0 STAC 0 Part A ST-OP-315-0031 0 STAl 0 Part B 0 LOR 0 Open Ref.

0 NOC Close Ref.

0 IN0 0 static

Question #61 Details EQ-OP-802-2001-000-0008-002 NRC RO Retake 2003 Question Text The plant is returning to operation after a refueling outage with power at 25%. The following conditions exist:

East Mechanical Vacuum Pump (MVP) ...................................... OFF West MVP................................................................................... OFF North Off Gas Ring Water Pump ................................................. Tripped South Off Gas Ring Water Pump ................................................. OFF 6D23 Off Gas 18" Manifold Pressure High .................................. ON 6D16 Off Gas Sys Mn Cond Press High ...................................... ON Steam Jet Air Ejector (SJAE) #1 ................................................... service SJAE #3 ................................................. ........................................ service What action should be taken and why?

Response A - Correct Answer Start the South Off Gas Ringwater Pump to prevent a turbine trip.

Reference:

2U.125.01 Response B Perform a rapid power reduction to prevent a further loss of vacuum.

Can't pcrforin at his lcvcl cxccpt by scram.

Response C Start MVPs to lower the 18" Manifold pressure.

Grcatcr than 5% power, can't start MVPs.

Response D Secure SJAE #1 to lower the 18" Manifold pressure.

SLart additional SJAE, not shut them down.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: Question ID: 34797 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO al l L 0 271000 K3.01 3.5 3.5 IziSRO 0ESP

References:

0 STAG Part A 20.125.01 STAl 0 Part B 0 LOR Open Ref.

NOC Et Close Ref.

0 IN0 0Static

Question #62 Details EQ-OP-315-0172-000-A021-001 NRC RO Retake 2003 Question Text The pre-action sprinkler system for the Warehouse A loading dock activates, causing flow in the Fire Protection Header and causing an Auto start of the Electric Fire Pump. Following isolation of the sprinkler what action(s) is(are) required to be performed to return the Electric Fire Pump to automatic standby?

When the demand on the fire water suppression system is removed and the jockey pump restores normal Fire Header pressure...

Response A The Electric Fire Pump automatically shuts down and returns to automatic standby.

'The Electric 'ire Pimp does not automatical1y shut down Response B Place Electric Fire Pump CMC switch in OFFRESET and back to AUTO in MCR.

Must be shut down locally.

Response C - Correct Answer Place Electric Fire Pump CMC switch in OFFRESET in MCR. Stop Electric Fire Pump locally. Place Electric Fire Pump CMC switch in AUTO.

Reference:

ST-OP-375-0072,23.501.01 Response D The Electric Fire Pump is Shutdown locally in the GSW pump house, which restores it to AUTO.

Shutting down locally doesn't restore to AUTO.

Author: BARRETT Keywords: FIRE PROT/DET Not Archived Date Last Used:

Time: 0 Question ID: 34796 Points: 1 ParentlD: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value a RO ElllL0 286000 A4.05 3.3 3.3 BSRO 0 ESP

References:

0 STAC 0 Part A ST-OP-315-0072 0 STAl [7 Part B 23.501.01 LOR Open Ref.

NOC Close Ref IN0 0 static

Question #63 Details EQ-OP-315-0116-000-A018-001 NRC RO Retake 2003 Question Text The plant has been operating at 100% thermal power. A transient occurs resulting in an elevated fission product release. The following conditions exist:

3D36 Div UII RB Vent Exh Radn Monitor Upscale trip is in alarm 33336 Div I/II RB Vent Exh Radn Monitor is in alarm Given the above conditions, what is the status of RB HVAC Fans and isolation dampers, and why?

Response A RB HVAC continues to operate normally to ensure Secondary Containment pressure remains negative.

RBHVAC is isolated due Secondary Containment Isolation.

Response B RB HVAC fans trip and isolation dampers remain open to ensure all effluent is processed through SGTS.

RBHVAC is isolated due Secondary Containment Isolation.

Response C - Correct Answer RB HVAC fans trip and isolate to stop the unfiltered release of radioactive particles to the environment .

Reference:

ST-OP-315-QOf6,2Q.000.02 Bases Response D RB HVAC fans trip and isolate to prevent overpressurizing the SGTS filter trains.

Has nothing to d o with overpressurization of the filter trains Author: BARRETT Keywords: CONTAINMENT Not Archived Date Last Used: RB HVAC Time: 0 SGTS Question ID: 34798 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 290001 K3.01 4.0 4.4 SRO ESP

References:

STAC 0 Part A ST-OP-315-0016 STAl [7 Part B 20.000.02 Bases LOR c]Open Ref.

c]NOC Close Ref, 0IN0 0 Static

Question #64 Details EQ-0P-802-200 1-000-0001-003 NRC RO Retake 2003 Question Text The plant is operating at 100%with the following conditions:

Control Room (CR) differential pressure ...................... 0.1"H20 and lowering Reactor Building (RB) differential pressure ..................-0.2" H20 and stable Turbine Building (TB) differential pressure.. .................-0.25" H20 and stable Div 1 CCHVAC Supply fan ....................................... Tripped Div 1 Master CMC Switch ......................................... Auto What should the operator do and why?

Response A Enter 20.413.01, Control Center HVAC Failure, start Div 2 CCHVAC to lower CR pressure.

Pressure needs to be raised.

Response B - Correct Answer Enter 20.413.01, Control Center HVAC Failure, start Div 2 CCHVAC to raise CR pressure.

Reference:

20.413.0#, ST-OP-315-0073 Response C Enter 23.413, Control Center HVAC, ensure Div 2 CCHVAC auto starts to lower CR pressure.

Pressure needs to be raised, there is no auto start.

Response D Enter 23.413, Control Center HVAC, ensure Div 2 CCHVAC auto starts to raise CR pressure.

Pressure needs to be raised, there is no auto start.

Author: BOLLINGER Keywords: CCHVAC Not Archived Date Last Used:

Time: 0 Question ID: 34800 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO PIILO 290003 2.4.1 1 3.4 3.6 SRO ESP

References:

STAC Part A 20.413.01 0 STAl Part B ST-OP-815-0073 LOR Open Ref.

[7 NOC Close Ref.

0IN0 Static

Question #65 Details EQ-OP-315-0102-000-B001-001 NRC RO Retake 2003 Question Text The reactor vessel flange low temperature limit of 7 1" may be adjusted during the design life of the plant to minimize the possibility of brittle fracture of the reactor pressure vessel and internals.

Which ONE of the following would cause the low temperature limit to be raised?

Response A - Correct Answer neutron embrittlement

Reference:

ST-OF-315-00Q2 Response 6 core shroud cracking Based on the vessel, not the shroud Response C chloride stress corrosion Low temp is not a factor of chloride stress corrosion Response D temperature embrittlement There is no such thing.

Author: BOLLINGER Keywords: RPV & INTERNALS Not Archived Date Last Used:

Time: 0 Question ID: 34783 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO m ILO 290002 K5.05 3.1 3.3 aSRO ESP

References:

0 STAC Part A ST-OP-315-0002 0 STAl 0 Part B 0 LOR Open Ref.

NOC Close Ref.

IN0 static

Question #66 Details EQ-OP-802-4101-000-0026-005 NRC RO Retake 2003 Question Text What does MOP07, Shift Turnover, say about performing major evolutions during shift turnover?

Response A Not allowed.

Not TAW with MOP7 Response B - Correct Answer Can continue with caution after obtaining supervisor permission.

Reference:

MOP07 Response C Can continue with caution after obtaining Operations Engineer permission.

Not IAW with MOP7 Response D Can continue with caution after Operations Manager permission.

Not TAW with MOP7 Author: BOLLINGER Keywords: ADMIN Not Archived Date Last Used:

Time: 2 Question ID: 34772 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO 0 110 generic 2.1.3 3.0 3.4 SRO 0 ESP

References:

c]STAC Part A MOP07 STAl Part B LOR c]Open Ref.

NOC a Close Ref.

c]IN0 static

Question #67 Details EQ-OP-008-0273-000-0104-011 NRC RO Retake 2003 Question Text The reactor mode switch is in the shutdown position with average reactor coolant temperature at 200°F, all control rods fully inserted, and all reactor vessel head bolts fully tensioned.

Which operating MODE is the unit in?

Response A MODE 2

-Mode switch in startup Response B - Correct Answer MODE 4

Reference:

Tech Spec Table 1.1-1 Response C MODE 5 Vessel head bolts are fully tensioncd Response D No specified MODE Were always it1 a Mode Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34773 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO a ILO Generic 2.1 2 2 2.8 3.3 a SRO 0 ESP

References:

STAC 0 Part A Tech Spec Table 1.1-1 0 STAI Part B LOR Open Ref.

0 NOC Close Ref.

IN0 Static

Question #68 Details EQ-OP-802-4101-000-0023-004 NRC RO Retake 2003 Question Text Performance of a pre-startup valve lineup will involve aligning a valve that is to be locked CLOSED. The valve in question is located in a high radiation area with the dose expected to be greater than 100 mrem. In this situation, independent verification of valve position Response A - Correct Answer may be waived by the Shift Manager

Reference:

MOP02 Response B shall be performed at the same time as the initial positioning Wouldnt be an indcpcndcnt veri Fication Response C may be performed by removing the locking device, checking the valve position, and re-installing the locking device Locking devices are not removed to check Iocked valve positions Response D shall be accomplished by visual verification that the locking device is properly installed An attempt to turn is to be inadc Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34774 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ElILO 294001 2.1.29 3.4 3.3 SRO 0 ESP

References:

STAC 0 Part A MOP02 STAl Part B 0 LOR fl Open Ref.

NOC a Close Ref.

fl IN0 0 static

Question #69 Details EQ-OP-315-0190-000-A017-001 NRC RO Retake 2003 Question Text Select the correct sequence of new fuel movement from receipt on the Refuel Floor to ready to place in the reactor.

Response A - Correct Answer Unloading Stand, New Fuel Inspection Stand, Fuel Preparation Machines, Fuel Storage Pool

Reference:

ST-OP-315-0190 Response B New Fuel Inspection Stand, Channel Gauging Stand, Fuel Preparation Machines, Fuel Storage Pool Wrong scqueiicc Response C New Fuel Inspection Stand, Fuel Preparation Machines, Channel Gauging Stand, Fuel Storage Pool Wrong sequence Response D New Fuel Inspection Stand, New Fuel Storage Vault, Fuel Preparation Machines, Fuel Storage Pool Wrong sequence Author: BARRETT Keywords: REFUELING Not Archived Date Last Used:

Time: 0 Question ID: 34799 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value a RO ElILO 234000 2.2.27 2.6 3.5 aSRO 0 ESP

References:

STAG Part A ST-OP-915-0190 0 STAl Part B LOR Open Ref.

NOC Close Ref.

IN0 El Static

Question #70 Details EQ-0P-315-0113-000-A018-001 NRC RO Retake 2003 Question Text The plant is shutting down for a mid-cycle outage.

Reactor Power is 20%.

The P603 operator inserted the selected Control Rod past its Group Insert Limit.

All other Control Rods are at their correct positions.

For these conditions, which of the following indications would result?

Response A An Insert Error and Insert Block In the transition Zone, only an Insert Error would be generated.

Response B A Withdraw Error and Withdraw Block In the transition Zone, only an Insert Error would be generated.

Response C - Correct Answer An Insert Error

Reference:

ST-OP-315-0013, ST-OP-315-OOi3 Response D A Withdraw Error.

In the transition Zone, only an Insert Error would be generated.

Author: BOLLINGER Keywords: RWM Not Archived Date Last Used:

Time: 2 Question ID: 34775 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO 110 201 006 2.2.33 2.5 2.9 SRO 0 ESP

References:

0 STAC 0 Part A ST-OPBI 5-0013 0 STAl 0 Part B 0 LOR 0 Open Ref.

0 NOC Close Ref.

0 IN0 0 Static

Question #71 Details EQ-OP-508-0001-000-A013-003 NRC RO Retake 2003 Question Text Which one of the following describes the annual limits for Total Effective Dose Equivalent (TEDE) as set forth in (1) 10CFR20 and (2) Fermi 2 Administrative Guidelines for those qualified as Full Radiation Worker?

Response A - Correct Answer 1.5000mrem

2. lOOOmrem

Reference:

ST-GN-508 Response B 1.5000mrem 2.500mrem Not IAW ST-GN-508 Response C 1.1500mrem

2. lOOOmrem Not IAW ST-GN-508 Response D

1. 1500mrem 2.500mrem Not IAW ST-GN-508 Author: BOLLINGER Keywords: -RO retake 2001 Not Archived Date Last Used: ADMlN Time: 2 Question ID: 34812 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO generic 2.3.1 2.6 3.0 a SRO 0 ESP generic 2.3.2 2.5 2.9 STAC Part A

References:

0 STAl 0 Part B ST-GN-508 0 LOR Open Ref.

0 NOC aClose Ref.

IN0 0 Static

Question #72 Details EQ-0P-31 5-0120-000-B007-002 NRC RO Retake 2003 Question Text In accordance with 23.406, Standby Gas Treatment System procedure; when performing a

- containment purge, the Standby Gas Treatment System (SGTS) should be used when ....

Response A RBHVAC is available.

This is opposite of what's in the procedure.

Response B effluent release monitoring is required.

Ef flucnt rcl ease monitoring i s always required Response C the containment is NOT completely inerted.

RBHVAC is thc prcfcrrcd choice Response D - Correct Answer needed to comply with the Effluent Release Limit.

Reference:

23.406 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 34777 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value aRO El ILO 2.3.9 2.5 3.4 aSRO ESP

References:

17 STAC 0 Part A 23.406 0 STAl I7 Part B LOR Open Ref.

0 NOC a Close Ref.

IN0 0 Static

Question #73 Details EQ-OP-802-3002-000-0006-027 NRC RO Retake 2003 Question Text During an emergency event in which a LOCA has occurred, RHR Loop B (Pumps B & D) is the only RPV injection available. The plant conditions are as follows:

RPV pressure ............................................... 150 psig RPV water level ........................................... -5 inches (steady)

Torus water level........................................... 80 inches (slowly decreasing)

RHR Loop B flow......................................... 20,000 gpm E1150-F015B7 Loop B Inbd Is0 Vlv .............Full open E1150-F017B7Loop B Otbd Is0 Vlv ............Full open The Nuclear Operator in the reactor building calls to report the running RHR pumps are rattling and beginning to vibrate severely.

The operating crew can continue to maintain long term adequate core cooling by:

Response A Raising the RHR loop flow to 22,000 gpm and RPV level well above TAF.

Might be true if flow wasnt already at max Response B Commence adding water to the torus in an effort to lower the water temperature.

Water temperature is not given Response C Lowering the RHR loop flow to 17,500 gpm even if RPV water level drops to -40 inches.

Dont lower flow once past L-6 and L-10 Response D - Correct Answer Allowing conditions to remain as they currently are since the RPV water level is above - 28 inches.

Reference:

EOP 29.100.01 SHI, EOP 29.100.01 SH6 Author: BOLLINGER Keywords: RHR - GENERAL Not Archived Date Last Used: VORTEX Time: 2 Question ID: 34801 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value aRO aILO 203000 K3.04 4.6 4.6 aSRO 0 ESP 203000 A2.16 4.4 4.5 0 STAC 0 Part A Generc 2.4.6 3.1 4.0 0 STAl Part B

References:

0 LOR aOpen Ref.

EOP 29.100.01 SH1 Step L-17 NOC 0 Close Ref.

EOP 29.100.01 SH6 0 IN0 0 Static

Question #74 Details EQ-OP-802-4101-000-0023-005 NRC RO Retake 2003 Question Text The plant is in an ATWS evolution. The CRS has directed the P603 operator to inject SLC.

In accordance with ODE- 10, Emergency Operating Procedure Expectations, what information MUST the P603 operator give the CRS when SLC is injecting?

Response A SLC is injecting, SLC pump discharge pressure, SLC tank level, and time injection started Not according to ODE- 10 Response B - Correct Answer SLC is injecting, SLC tank level, and time injection started

Reference:

ODE-10 Response C SLC is injecting, time ifljection started Not ~ c c o ~ ~ ~toI ODE-I:: IO Response D SLC is injecting Not according to ODE-10 Author: BOLLINGER Keywords: SAG Not Archived Date Last Used:

Time: Question ID: 34778 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO a ILO Generic 2.4.13 3.3 3.9 aSRO 0 ESP

References:

STAC 0 Part A ODE4 0 0STAl Part B 0 LOR 0 Open Ref.

0 NOC Close Ref.

0 IN0 0 Static

Question #75 Details EQ-OP-802-4101-000-0028-004 NRC RO Retake 2003 Question Text In accordance with MOP10, "Fire Brigade", which of the following is a requirement for Fire Brigade members?

Response A Hold an active RO or SRO License Not according to MOP1 0 Response B CompIetely qualified as a Nuclear Operator Not according to MOP f 0 Response C - Correct Answer Up to date radworker qualifications

Reference:

MOP1 0 Step 3.1.3 Response D Up to date confined space qualifications Not according to MOP 10 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 2 Question ID: 34779 Points: 1 Parent ID: 0 Cognitive Level: 1 Child ID: 0 KA System KA Number RO Value SRO Value a RO ElILO 286000 2.4.26 2.9 3.3 aSRO ESP

References:

STAC Part A MOP10 STAl Part B LOR 0 Open Ref.

0 NOC Close Ref.

IN0 Static