ML043000355

Sept 2004 RO Initial Exam

ML043000355
Person / Time
Site:	Fermi
Issue date:	11/05/2004
From:	Pederson C Division of Reactor Safety III
To:	O'Connor J Detroit Edison
References
50-341/04-301
Download: ML043000355 (75)

Text

Question #1 Details EQ-OP-315-0121-000-B003-001 2004 RO NRC Exam Question Text The plant is operating at 53% power.

Preparations have been made to transition to single loop operations.

Conditions are as follows:

A MG set speed.....30%

B MG set speed.....73%

Total Core flow...57%

Which of the following describes how B loop flow and total core flow indication will respond when the A MG set is tripped?

Response A B flow indication remains constant and total flow indication lowers due to flow through loop A being subtracted from loop B.

B flow does not remain constant. Total flow indication answer is correct.

Response B B flow indication remains constant and total flow indication lowers due to less backpressure on Recirc Pump B.

B flow does not remain constant. Back pressure may change but is not why the indication changes.

Response C - Correct Answer B flow indication will rise and total flow indication lowers due to flow through loop A being subtracted from loop B.

Reference 1 Response D B flow indication will rise and total flow indication lowers due to less backpressure on Recirc Pump B.

B Indication will rise. Back pressure may change but is not why the total flow indication changes.

Author: BOLLINGER Keywords: RRS Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35292 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295001 A2.06 3.2 3.3  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0021 INO Static

Question #2 Details EQ-OP-315-0165-000-C014-002 2004 RO NRC Exam Question Text Emergency Diesel Generator (EDG) 14 is paralleled to EDG Bus 14ED and is loaded to 1800kW. A lightning strike causes a loss of off-site power.

Which of the following describes the EDG System response?

Response A EDG 14 output breaker will trip, load shed will occur, EDG 14 will continue to run, and the output breaker will remain open Although the output breaker will trip, the EDG will not shut down.

Response B - Correct Answer EDG 14 output breaker will trip, load shed will occur, EDG will continue to run, and the output breaker will reclose.

Reference:

1 Response C EDG 14 output breaker will remain closed, EDG 14 will shutdown, and then restart in isochronous mode The EDG will remain running, and output breaker trips. The EDG will be in isochronous, but does not restart.

Response D EDG 14 output breaker will remain closed, EDG 14 will continue running and the governor will shift to isochronous mode.

Output breaker opens, diesel does operate in isochronous, but after the output breaker re-closes.

Author: BOLLINGER Keywords: 120/345 kV Not Archived Date Last Used: SWITCHYARDS EDG Time: 3 2004 NRC RO Question Question ID: 35250 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295003 K2.02 4.1 4.2 SRO ESP 264000 K1.01 3.8 4.1 STAC Part A 264000 A2.07 3.5 3.7 STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0065 INO Static

Question #3 Details EQ-OP-315-0164-000-A021-001 2004 RO NRC Exam Question Text The reactor has scrammed.

A Loss of Offsite Power has occurred.

Only EDGs 13 & 14 have started and loaded.

No other operator actions have occurred.

What is the source of power to the station DC loads?

Response A Div 1 DC loads - supplied by the Div 1 Batteries Div 2 DC loads - supplied by the Div 2 Battery Chargers Battery Chargers do not get reenergized by the Load Sequencer. Div 2 EDGs starting make this choice plausible if this not known.

Response B Div 1 DC loads - supplied by the Div 2 Battery Chargers Div 2 DC loads - supplied by the Div 2 Battery Chargers Battery Chargers do not get reenergized by the Load Sequencer. Div 2 EDGs starting and not knowing the DC system lineup make this choice plausible.

Response C Div 1 DC loads - supplied by the Div 1 Battery Chargers Div 2 DC loads - supplied by the Div 2 Batteries Battery Chargers do not get reenergized by the Load Sequencer. Not knowing the DC system lineup or EDG lineup make this choice plausible.

Response D - Correct Answer Div 1 DC loads - supplied by the Div 1 Batteries Div 2 DC loads - supplied by the Div 2 Batteries Battery Chargers do not get reenergized by the Load Sequencer.

References:

1, 2, 3 Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 0 Question ID: 35295 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295004 K2.01 3.1 3.1 SRO ESP STAC Part A

References:

STAI Part B ST-OP-315-0064 LOR Open Ref.

20.300.OFFSITE Step AP NOC  ; Close Ref.

20.300.OFFSITE Bases INO Static

Question #4 Details EQ-OP-315-0055-000-A010-001 2004 RO NRC Exam Question Text While operating at 100% power, the Generator Field Breaker 41Cs on COP H11-P804 opens, causing a generator trip.

The generator trip occurred to protect against which ONE of the following?

Response A Phase to phase faults in the stator windings.

Basis for the generator differential trip, not the loss of excitation trip.

Response B Phase to ground faults in the main transformer.

Basis for transformer over excitation trip Response C - Correct Answer Excessive current in the generator rotor.

Reference 1, 2 Response D Over voltage on the main transformer.

Protection for the transformer is an over excitation trip, not over voltage. (see response B) Still not the basis for the field breaker trip, although a good distractor.

Author: BOLLINGER Keywords: TURBINE STEAM Not Archived Date Last Used: RPS Time: 5 2004 NRC RO Question Question ID: 35284 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295005 K3.04 3.2 3.2 SRO ESP STAC Part A

References:

STAI Part B 23.118 Step 3.11 LOR Open Ref.

ST-OP-315-0055 NOC  ; Close Ref.

INO Static

Question #5 Details EQ-OP-315-0104-000-B004-003 2004 RO NRC Exam Question Text Following a Reactor Scram from full power total feedwater flow is 15%. The Operator checks the speed of the Recirculation Pumps.

What should the Recirculation Pumps speed be?

Response A - Correct Answer 30%

References 1, 2 Response B 37%

Close to Limiter #2/3 Response C 40%

Limiter #2/3, doesnt meet conditions for the limiter.

Response D 48%

Close to Limiter #2/3 , doesnt meet conditions for the limiter.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35285 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295006 AK3.06 3.2 3.3  ; SRO ESP 295006 A1.04 3.1 3.2 STAC Part A STAI Part B

References:

LOR Open Ref.

NOC  ; Close Ref.

ST-OP-315-0004 INO Static

Question #6 Details EQ-OP-315-0099-000-A012-001 2004 RO NRC Exam 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. In accordance with the procedure, the Main Turbine has been tripped before exiting the Control Room.

What is the purpose of tripping the Main Turbine?

Response A Prevent MSIV isolation from low pressure.

Nothing states there would be lowering pressure. Preferred if MSIVs open to maintain pressure with bypass valves.

Response B - Correct Answer Allow bypass valves to control pressure and heat rejection.

This is preferred, but SRVs can do the same. Reference ST-OP-315-0099 (1), (2), 20.000.19 Response C Allow SRVs A and B to control pressure from the Dedicated Shutdown Panel.

SRV G is controlled from the Dedicated Shutdown Panel. SRVs A and B can be controlled from the Remote Shutdown Panel. The differences are sometimes confused, making this a plausible distractor.

Response D Prevent a high RPV level trip of the Main Turbine.

The SULCV should be maintaining level if the RFP are running, nonetheless, this is not the reason.

Author: BOLLINGER Keywords: DEDICATED S/D Not Archived Date Last Used:

Time: 3 Question ID: 35445 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295016 K3.02 3.7 3.8  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

20.000.19 NOC  ; Close Ref.

ST-OP-315-0099 INO Static

Question #7 Details EQ-OP-315-0167-000-B003-002 2004 RO NRC Exam Question Text With the plant operating at full power, P4400-F603B, Div 2 EECW Supply Iso Vlv has failed closed.

Which ONE of the following must be taken to ensure cooling to the CRD pumps?

Response A

- Verify auto start of Div 2 EECW and EESW pumps Not completely correct. The pumps auto start, but further actions must be taken to ensure cooling to CRD pumps.

Response B - Correct Answer

- Verify auto start of Div 2 EECW and EESW pumps

- Depress Div. 2 EECW Iso Reset Switch

- Open P4400-F604, Div 2 EECW to CRD Sply Iso Vlv Closing P4400-F603B causes an auto start of EECW/EESW.

References:

ST-OP-315-0067(1), (2)

Response C

- Close P4400-F601B, Div 2 EECW Return Iso Vlv

- Start Div. 2 EECW and EESW pumps

- Open P4400-F604, Div 2 EECW to CRD SPLY Iso Vlv F601B will auto close, Div.2 EECW and EESW auto start.

Response D

- Place Div 2 EECW Iso Override Sw keylock switch in MANUAL OVERRD

- Depress Div 2 EECW Iso reset Switch

- Open P4400-F604, Div EECW to CRD Sply Iso Vlv Placing Div 2 EECW Iso Override Sw keylock switch in MANUAL OVERRD prevents all operation of EECW and EESW.

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35313 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295018 K3.07 3.1 3.2 SRO ESP 295018 K1.01 3.5 3.6 STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0067 NOC  ; Close Ref.

INO Static

Question #8 Details EQ-OP-315-0171-000-A008-001 2004 RO NRC Exam Question Text Which one of the following describes the operation and function of P50-F402, Station Air to Instrument Air Isolation Valve, during a loss of air event?

Response A - Correct Answer Closes to isolate the safety related control air from the station air supply The P50-F402 closes when station air drops to 72psig. Reference ST-OP-315-0071 Response B Closes to separate the two divisions of NIAS, from each other, to ensure redundancy.

P50-F440 and P50-F440 close to isolate NIAS, P50-F402.

Response C Opens to crosstie the Interruptible Air Supply to allow the Station Air Compressors to supply Division 2 NIAS.

The valve does not open, P50-F403 crossties Div 2 NIAS to IAS.

Response D Opens to allow the safety related Control Air Compressors to supply each division of NIAS.

The valve does not open, P50-F440 and P50-F440 actually close to isolate NIAS.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35317 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295019 K3.03 3.2 3.2  ; SRO ESP 295019 2.1.27 2.8 2.9 STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0071 NOC  ; Close Ref.

INO Static

Question #9 Details EQ-OP-802-2001-000-R008-003 2004 RO NRC Exam Question Text The plant is in extended maintenance shutdown in Mode 4 when a loss of shutdown cooling occurs. Shutdown cooling cannot be immediately restored to either loop of RHR.

The North Reactor Recirc pump is running.

Which ONE of the following is an allowable option for alternate shutdown cooling under these conditions?

Response A - Correct Answer RWCU Blowdown to the Main Condenser, makeup with a SBFW pump.

Reference : 23.800.04 Page 7 Response B Alternate shutdown cooling not required, Recirc pump is running.

Recirc pump is used to promote circulation, but has no heat removal capacity.

Response C Bleed Steam via SRVs when pressure reaches 100 psig, makeup with Core Spray.

Only done when Recirc pumps are not available.

Response D Bleed Steam via Bypass Valves when pressure reaches 50 psig, makeup with SBFW.

Not an acceptable method per procedure.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID:

Points: 1 Parent ID:

Difficulty: 2 Child ID:

KA System KA Number RO Value SRO Value  ; RO  ; ILO 295021 A1.01 3.4 3.4  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

20.800.04 NOC  ; Close Ref.

INO Static

Question #10 Details EQ-OP-802-2001-000-R006-004 2004 RO NRC Exam Question Text An irradiated fuel bundle is being removed from the core. An adjacent bundle has been lifted along with the selected bundle. When noticed, fuel movement is stopped, and the non-selected bundle falls back into the core.

Bubbles come to the pool surface, and the local Continuous Air Monitor (CAM) alarms.

16D1, Refueling Floor High Radiation has alarmed.

What other automatic actions would occur as a result of this alarm?

Response A RBHVAC isolates.

RBHVAC would isolate on a refueling building exhaust high radiation, not an area alarm.

Response B - Correct Answer No automatic actions happen.

Reference:

16D1, Page 1 Response C CCHVAC System shifts to PURGE mode.

CCHVAC shifts to RECIRC mode on refueling building exhaust high radiation.

Response D Primary Containment Purge / Vent valves close.

Fuel Pool Exhaust Rad monitor will cause a secondary containment isolation, not the area alarm.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35409 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295023 A2.01 3.6 4.0  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

16D1 NOC  ; Close Ref.

INO Static

Question #11 Details EQ-OP-802-3002-000-0006-033 2004 RO NRC Exam Question Text Drywell sprays are initiated within the safe region of the Drywell Spray Initiation Limit Curve to preclude?

Response A - Correct Answer Primary containment failure due to differential pressure.

The negative pressure capability could be challenged.

Reference:

ST-OP-802-3002 Response B Excess hydrogen generation due to atomization of cooling water.

Although the cooling water is assumed to vaporized instantly, there is no hydrogen generation.

Response C An uncontrolled rise in drywell pressure due to the flashing of steam of the drywell spray water.

There could be an uncontrolled drop in pressure vs. rise in pressure.

Response D An uncontrolled pressure drop due to the displacement of Nitrogen from the drywell to the Torus.

Although there could be an uncontrolled pressure drop due to the deinerting of the drywell, the flow path is from the torus to the drywell.

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35381 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295024 K1.01 4.1 4.0  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-802-3002 NOC  ; Close Ref.

INO Static

Question #12 Details EQ-OP-315-0105-000-B004-001 2004 RO NRC Exam Question Text A pressure transient has occurred with reactor pressure exceeding the reactor scram setpoint and initiating a reactor scram.

RPV pressure is 1000 psig and rising slowly.

Which of the following describes the expected indications if this transient resulted in a leaking SRV?

Response A SRV Tailpipe temperature approximately 520°F; red SRV OPEN light ON.

0 Temperature of 520 F would indicate SRV open, not leaking. SRV OPEN light ON is based on pressure limit, and the limit would not be reached for a leaking SRV.

Response B SRV Tailpipe temperature approximately 520°F; SRV OPEN Annunciator 1D61 ON.

Temperature of 5200F would indicate SRV open, not leaking. SRV OPEN Annunciator 1D61 ON is correct.

Response C SRV Tailpipe temperature approximately 260°F; red SRV OPEN light ON.

Temperature is correct. SRV OPEN light ON is based on pressure limit, and the limit would not be reached for a leaking SRV.

Response D - Correct Answer SRV Tailpipe temperature approximately 260°F; SRV OPEN Annunciator 1D61 ON.

Temperature is correct, causes Annunciator 1D61.

Reference:

ST-OP-315-0005(1) (2)

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35335 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295025 K1.03 3.6 3.8  ; SRO ESP 295025 A1.03 4.4 4.4 STAC Part A STAI Part B

References:

LOR Open Ref.

ARP 1D61 NOC  ; Close Ref.

ST-OP-315-0005 INO Static

Question #13 Details EQ-OP-315-0127-000-A018-005 2004 RO NRC Exam Question Text The plant is operating at 100% power.

A failure of the governor/pressure regulator occurs which causes the turbine control valves to fully open.

Which one of the following RPS functions will scram the reactor?

Response A- Correct Answer Main Steam Isolation Valve Closure Provided to limit the amount of fission product release.

Reference:

ST-OP-315-0027 Response B APRM flux - Upscale The setpoints are selected to provide adequate margin for the Safety Limits.

Response C Low RPV water level The reactor vessel water level trip setpoint was chosen far enough below the normal operating level to avoid spurious trips but high enough above the fuel to assure that there is adequate protection for the fuel and pressure limits.

Response D Turbine Stop Valve Closure The turbine stop valve closure trip anticipates the pressure, neutron flux, and heat flux increases that would result from closure of the stop valves Author: BOLLINGER Keywords: RPS Not Archived Date Last Used:

Time: 3 Question ID: 35370 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 212000 2.1.27 2.8 2.9  ; SRO ESP 295025 A2.02 4.2 STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0027 NOC  ; Close Ref.

INO Static

Question #14 Details EQ-OP-802-3002-000-0006-032 2004 RO NRC Exam Question Text During an ATWS, boron injection must be started before torus water temperature reaches a certain limit.

What is the reason for injecting before this temperature?

Response A - Correct Answer Ensure the reactor is shutdown before exceeding the torus water temperature upper limit.

Preclude exceeding the Heat Capacity Limit, which would require emergency depressurization.

Reference:

1 Response B Prevent opening torus to drywell vacuum breakers.

Higher temperature in the torus could cause the breakers to open, but its not the reason boron is injected.

Response C Allow continued RCIC operation.

Although torus temperature can limit RCIC operation, its not the specific reason boron is injected.

Response D Ensure adequate NPSH for LPCI.

Although there is a limit for NPSH, its not related to SLC injection.

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

Time: 3 Question ID: 35371 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295026 2.4.18 2.7 3.6  ; SRO ESP STAC Part A

References:

STAI Part B 29.100.01 Sh 6 LOR Open Ref.

ST-OP-802-3002 NOC Close Ref.

INO Static

Question #15 Details EQ-OP-802-3002-000-0005-006 2004 RO NRC Exam Question Text A LOCA has occurred outside of the primary containment. Plant conditions are as follows:

Reactor Building Temperature (near all instrument runs) - 220oF and stable.

Reactor Pressure - 250 psig and stable.

Drywell Temperature - 155oF and stable.

Assuming the indicated level on each of the below instruments is 163 inches, which level instrument may be used for trending indication?

Response A Flood Up Minimum indicated level is 190 inches between 150 and 250oF Response B Narrow Range Maximum RB run temperature of 103 oF Response C - Correct Answer Wide Range See Reference 29.100.01 Sheet 6 Caution 3.A Response D Core Level Maximum upper range is 50 inches.

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 0 Question ID: 35417 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295028 K1.01 3.5 3.7  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

29-100-01 SH 6 NOC  ; Close Ref.

INO Static

Question # 15 Handout Question #16 Details EQ-OP-315-0139-000-B003-002 2004 RO NRC Exam Question Text Due to a valving error the torus water level has reached a low Torus Water Level EOP entry point. What automatic action is expected to occur at this point?

Response A RCIC suction will shift to the CST.

RCIC switches from the CST to the Torus based on CST level, not Torus level.

Response B HPCI suction will shift to the CST.

The EOP LOW entry condition is -2 inches, not +2 inches.

Response C - Correct Answer The Torus Water Management System pumps will trip.

Reference ST-OP-315-0069 (1), (2)

Response D The Torus Water Management System torus suction valves will close.

Action is wrong. Plausible because there is a Group 12 isolation that closes these valves on torus sump level of +39 inches.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 2 Question ID: 35375 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295030 A2.1 4.1 4.2  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0069 NOC  ; Close Ref.

7D71 INO Static

Question #17 Details EQ-OP-315-0142-000-A021-003 2004 RO NRC Exam Question Text While the plant was operating in Mode 1, a LOCA and Loss of Offsite Power occurred and the following conditions exist :

RPV water level........................................+ 76 inches (lowering 4 inches/min)

DW pressure..............................................................17.5 psig (slowly rising)

EDGs..............................No. 14 ONLY running supplying associated ESF Bus Given the above parameters and assuming no operator action involving ADS, identify which of the following describe the expected response of the ADS System.

If the low pressure ECCS Systems function as designed, ADS will begin depressurizing the plant:

Response A - Correct Answer in approximately 13 minutes.

High DW pressure and L1 after 11 minutes plus 105 minutes ~ 13 minutes.

Reference:

ST-OP-315-0042 Figure 4 Response B in approximately 20 minutes.

Could be thought correct if the 7 minute wait on RPV level less than Level 1 is mistaken.

Response C 105 seconds following EDG 11 restart.

The logic has to satisfy high DW pressure AND L1 or L1 greater than 7 minutes, then 105 sec timer, then satisfy pumps running portion of logic.

Response D 525 seconds following EDG 12 restart.

The logic has to satisfy high DW pressure AND L1 or L1 greater than 7 minutes, then 105 sec timer, then satisfy pumps running portion of logic. 7 minutes and 105 seconds = 525 seconds.

Author: BOLLINGER Keywords: ADS Not Archived Date Last Used: 2004 NRC RO Question Time: 4 Question ID: 35376 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 218000 K5.01 3.8 3.8  ; SRO ESP 218000 2.1.28 3.2 3.3 STAC Part A 295031 K2.08 4.2 4.3 STAI Part B

References:

LOR Open Ref.

23.201 NOC  ; Close Ref.

LP-OP-315-0142 INO Static

Question #18 Details EQ-OP-802-3002-000-0008-011 2004 RO NRC Exam Question Text The plant has experienced an ATWS and SLC has been injected.

Which of the following items is assumed in determining the Hot Shutdown Boron Weight?

Response A RPV voids are at maximum.

No voids are assumed Response B No Xenon is present in the core.

No practical for after a power change.

Response C - Correct Answer RPV water level is at the high level trip setpoint.

Reference:

ST-OP-8002-3002 Response D RWCU is in normal operation.

Would be isolated when SLC is initiated.

Author: BOLLINGER Keywords: EOP RPV Power Not Archived Date Last Used: EOP Alt Boron Inj Time: 2 ATWS Question ID: 35475 Points: 1 SLC Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295037 K3.01 4.4 4.5  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

NOC  ; Close Ref.

INO Static

Question #19 Details EQ-OP-832-0001-000-0005-004 2004 RO NRC Exam Question Text An accident has happened at Fermi 2 that causes the Shift Manager to declare an UNUSUAL EVENT.

A short time later, radiation levels at the site boundary reach 11 mr/hr, and the Shift Manager declares an ALERT.

Which ONE of the following describes what happens at an ALERT that did not happen at UNUSUAL EVENT?

Response A Radiological Emergency and Personnel Monitoring Teams are activated.

Also done at an UNUSUAL EVENT Response B Offsite Protective Action Recommendations (PARS) are calculated.

Emergency Plan provides for protection of all members of the public Response C Joint Public Information Center (JPIC) is activated.

Done at Site Area Emergency.

Response D - Correct Answer Assembly and accountability is ordered in the Protected Area.

Reference : EP-103 Page 6 Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35394 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295038 K3.01 3.6 4.5  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

EP-103 NOC  ; Close Ref.

INO Static

Question #20 Details EQ-OP-315-0172-000-C001-001 2004 RO NRC Exam Question Text A fire has occurred in the plant. A smoke damper has isolated a HVAC system due to a suppression system initiation.

What must be done to re-open the smoke damper?

The damper is....

Response A reset locally, then opened.

Actually reset from the Control Room.

Response B reset locally, opens automatically.

Actually reset from the Control Room, no automatic opening.

Response C disassembled and the fusible link replaced.

This would be correct for a fire damper, not a smoke damper.

Response D - Correct Answer opened from the Control Room.

Reference:

ST-OP-315-0072 Author: BOLLINGER Keywords: FIRE PROT/DET Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35378 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 600000 A1.05 3.0 3.5  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0072 NOC  ; Close Ref.

INO Static

Question #21 Details EQ-OP-315-0141-000-A015-001 2004 RO NRC Exam Question Text The plant is in Mode 3 with RHR Div 1 in Shutdown Cooling operation.

RHR pump A is running.

Annunciator 1D33, RHR System Overpressure, is received.

Which one of the following describes the plant response to this condition?

Response A Group 3 isolation and RHR pump A trip.

Group 3 is an RHR isolation on Level 1 or Hi drywell pressure, RHR pump A trip would trip on Group 4 not a Group 3.

Response B Group 4 isolation and RHR pump A continues to run.

Group 4 isolation is based on overpressure and is correct, but the RHR pump A would trip if there was a Group 4 isolation.

Response C Group 3 isolation and RHR pump A continues to run.

Group 3 is an RHR isolation on Level 1 or Hi drywell pressure, RHR pump A continuing to run would be correct for Group 3.

Response D - Correct Answer Group 4 isolation and RHR pump A trip.

Group 4 isolation is based on overpressure, pump trips due to low suction pressure.

Reference:

ST-OP-315-0048, ST-OP-315-0041.

Author: BOLLINGER Keywords: RHR - SDC Not Archived Date Last Used: PCIS Time: 2 2004 NRC RO Question Question ID: 35379 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295007 K2.06 3.5 3.7  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0041 NOC  ; Close Ref.

ST-OP-315-0048 INO Static

Question #22 Details EQ-OP-315-0139-000-C001-001 2004 RO NRC Exam Question Text HPCI and RCIC have automatically started following a loss of feedwater.

RPV level increases to 220 inches, and a short time later HPCI turbine speed is 0 RPM.

As RPV level begins to decrease below 160 inches the CRS directs HPCI to be restarted.

What action is taken to restart HPCI?

Response A Open E4150-F001 turbine steam supply isolation valve.

The trip logic is automatically reset at Level 2, wont be able to open this valve.

Response B Open E4150-F003 HPCI steam supply outboard isolation valve.

The trip logic is automatically reset at Level 2, wont be able to open this valve.

Response C Depress the HPCI initiation signal reset pushbutton and start the aux oil pump.

There is no initiation signal present, so resetting will have no effect.

Response D - Correct Answer Depress the reactor high water level signal reset pushbutton.

The trip logic is automatically reset at Level 2, to restart before Level 2, the trip signal must be reset.

Reference:

ST-OP-315-0039, 23.202 page 35.

Author: BOLLINGER Keywords: HPCI Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35380 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295008 A1.04 3.5 3.5  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

23.202 NOC  ; Close Ref.

ST-OP-315-0039 INO Static

Question #23 Details EQ-OP-315-0121-000-A012-001 2004 RO NRC Exam Question Text A plant transient has occurred. Plant conditions are:

Mode 3 RPV level is 170" RPV pressure is 950 psig.

Recirc Pumps A & B have tripped.

Which RPV level instrument would provide the most accurate level reading at this time based on its calibration conditions?

Response A Narrow Range Calibrated for best indication with jet pumps running.

Response B - Correct Answer Wide Range

Reference:

ST-OP-315-0021 Response C Floodup Calibrated for 0 Psig, 120oF, with no jet flow.

Response D Core Level Outside the calibrated level band of 150 to 50 inches.

Author: BOLLINGER Keywords: RPV INST Not Archived Date Last Used:

Time: 0 Question ID: 35453 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295009 K2.01 3.9 4.0  ; SRO ESP STAC Part A STAI Part B References LOR Open Ref.

ST-OP-315-0021 NOC  ; Close Ref.

INO Static

Question #24 Details EQ-OP-802-3002-000-0004-022 2004 RO NRC Exam Question Text During an event in the plant, an SRV has opened, causing Torus temperature to reach 120oF. What is the significance of torus water level dropping to -14 inches?

Response A Terminate operation of LPCI due to exceeding pump NPSH limits.

The LPCI NPSH limits are not in effect until 167oF.

Response B Obtain torus water temperatures from the T23-R800A/B, Suppression Chamber Bulk Water Temperature Recorder on the H11-P601 panel.

All of the thermocouples providing input to this recorder are uncovered and will indicate air temperature at this level.

Response C - Correct Answer Obtain torus water temperatures from T50-R800A/B, Primary Containment Air and Water Temperature recorders on the H11-P601 / P602 panels.

Reference:

ST-OP-802-3002 Response D Terminate operation of HPCI due to exceeding high oil temperatures.

This limit is not considered until 140oF.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35385 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295013 A2.01 3.8 4.0  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-802-3002 NOC  ; Close Ref.

INO Static

Question #25 Details EQ-OP-802-3005-000-0010-010 2004 RO NRC Exam Question Text The first override statement in the Secondary Containment EOP states that if RB HVAC or fuel pool vent exhaust radiation levels exceeds certain limits, then the operator shall confirm isolation of RB HVAC and initiation of SGTS.

Which of the following best describes why the above must be confirmed or manually initiated?

Response A Confirming isolation of RBHVAC subsequent to receipt of a high radiation signal terminates any further release of radioactivity to the Reactor Building from this system.

RBHVAC actually exhausts air from the Reactor Building, not the other way around.

Response B - Correct Answer SGTS is the normal mechanism employed under post-transient conditions to maintain Reactor Building Pressure negative with respect to the atmosphere.

Reference:

ST-OP-8002-3005 Response C Exhaust from SGTS is processed and directed to an elevated release point before being discharged to the Reactor Building.

Exhaust from the SGTS is discharged to atmosphere.

Response D Operation of SGTS will ensure that the Control Room envelope is maintained at a positive pressure.

SGTS designed to maintain negative pressure in the Reactor Building.

Author: BOLLINGER Keywords: Archived Date Last Used:

Time: 3 Question ID: 28725 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295017 K3.02 3.3 3.5  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-802-3005 NOC  ; Close Ref.

INO Static

Question #26 Details EQ-OP-315-0173-000-B003-001 2004 RO NRC Exam Question Text The plant is operating at 100% power with Division 1 of Control Center Heating, Ventilation and Air Conditioning (CCHVAC) in service, when the following alarms occur:

3D32, Div I/II RB Vent Exh Radn Monitor Upscale 3D36, Div I/II RB Vent Exh Radn Monitor Upscale Trip How do the following CCHVAC components respond?

Response A Division 2 North and South Emergency Intake Dampers opens.

Only the Division 1 Emergency Intake Dampers Open.

Response B - Correct Answer Division 1 Normal Intake Dampers close.

Reference ST-OP-315-0027 Response C Division 2 Makeup Air Fan stops.

These fans start, but one Division must be stopped manually to prevent exceeding pressure limits.

Response D Division 1 Return Air Fan stops.

These fans will not stop.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 5 Question ID: 35387 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295033 A1.08 3.6 3.8  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

LP-OP-315-0173 NOC  ; Close Ref.

3D36 INO Static

Question #27 Details EQ-OP-802-3004-000-0013-004 2004 RO NRC Exam Question Text The plant has experienced a transient that requires emergency depressurization due to high drywell hydrogen and oxygen levels.

Why would the crew perform this emergency depressurization?

Response A - Correct Answer Burning of these gasses may damage equipment important to the safe shutdown of the plant.

Reference:

ST-OP-802-3002 Response B Hydrogen and oxygen concentrations can be prevented from exceeding explosive limits.

The ED happens at explosive limits, so the limits have been exceeded.

Response C Hydrogen and oxygen concentrations are outside the limits for safe operation of the recombiners.

Although this is true for the recombiners, its not true for the reason for ED.

Response D Spraying the drywell is ineffective at these levels of hydrogen and oxygen.

Spraying is not ineffective, has nothing to do with ED.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35224 Points: 1 Parent ID: 34091 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 500000 K3.04 3.1 3.9  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-802-3002 NOC  ; Close Ref.

INO Static

Question #28 Details EQ-OP-315-0141-000-A021-011 2004 RO NRC Exam Question Text The plant has experienced a LOCA with the following conditions:

EDG................................................13 not running RPV Level...................................25 inches RPV Pressure..................................425 psig Drywell Pressure..............................2.5 psig Torus Water Temperature................128°F A Reactor Recirc MG set.................tripped B Reactor Recirc MG set.................tripped B3105-F031A, Recirc Loop A discharge isolation valve, is shut.

What is the current status of the RHR system?

Response A RHR pumps A, C & D are running, injecting into Loop A No injection until about 300 psig, theres been no LOOP, so EDG 13 not running doesnt matter.

Response B All RHR pumps are running, injecting into Loop A All pumps are running, but no injection because of the RPV pressure.

Response C RHR pumps A, C & D are running and not injecting All pumps are running, since theres been no LOOP Response D - Correct Answer All RHR pumps are running and not injecting

Reference:

ST-OP-315-0041 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35443 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 203000 A1.01 4.2 4.3  ; SRO ESP STAC Part A

References:

STAI Part B LOR Open Ref.

ST-OP-315-0041 NOC  ; Close Ref.

INO Static

Question #29 Details EQ-OP-315-0141-000-A013-001 2004 RO NRC Exam Question Text The General Operating Procedure for reactor shutdown and cooldown directs the operator to raise RPV water level to above 220" prior to entering Shutdown Cooling (SDC).

What is the reason for raising water level above the normal level?

Response A Ensures adequate NPSH for RHR pumps.

Incorrect because NPSH for RHR pumps is a function of Torus Temp and RPV level.

Response B Satisfies the interlock required for opening RHR SDC valves.

Incorrect because RHR SDC valve interlock is >L3.

Response C Provides additional inventory for RHR system warmup in preparation for SDC.

Incorrect because 220 has nothing to do with inventory for piping warmup Response D - Correct Answer Provides adequate natural circulation to minimize temperature stratification during SDC.

Reference:

22.000.04 Reactor shutdown procedure, page 37, ST-OP-315-0141 Author: CADDEN Keywords: RHR - SDC Not Archived Date Last Used: 10/23/2000 2004 NRC RO Question Time: 3 Question ID: 35386 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 295009 K1.05 3.3 3.4  ; SRO ESP 205000 K5.03 2.8 3.1 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

22.000.04 Reactor shutdown procedure, page 37 INO Static ST-OP-315-0141

Question #30 Details EQ-OP-315-0139-000-A021-004 2004 RO NRC Exam Question Text During an AUTOMATIC initiation of HPCI, the HPCI Pump flow is 5200 GPM.

The E4150-F012 Pump Min Flow Valve fails open.

Five minutes later, the HPCI system will have:

Response A - Correct Answer raised HPCI turbine speed.

Reference:

ST-OP-315-0039 Response B lowered HPCI turbine speed.

The HPCI controller is attempting to maintain 5200 gpm going to the RPV, so speed will not be lowered.

Response C indicated HPCI flow greater than 5200 GPM.

Indicated flow will stay at 5200 gpm, since the controller senses flow going to the vessel.

Response D indicated HPCI flow less than 5200 GPM.

Indicated flow will stay at 5200 gpm, since the controller senses flow going to the vessel.

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

Time: 2 Question ID: 30766 Points: 1 Parent ID: 29955 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 206000 K3.01 4.0 4.0  ; SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0039 NOC  ; Close Ref.

INO Static

Question #31 Details EQ-OP-315-0139-000-A021-003 2004 RO NRC Exam Question Text High Pressure Coolant Injection (HPCI) has automatically initiated with the following indications:

Reactor water level.............................................+40" on WR level instrument HPCI Barometric condenser condensate pump.....................................running HPCI Barometric condenser vacuum pump..........................................running HPCI Auxiliary Oil pump................................................................not running HPCI flow......................................................................................5,000 gpm RPV level subsequently drops to +20 inches on WR level indication. How should HPCI respond?

Response A HPCI auxiliary oil pump will auto start Incorrect because the aux oil pump is not required while HPCI is at rated speed Response B HPCI flow will increase to 5,200 gpm Incorrect because the flow controller has not been changed Response C - Correct Answer HPCI Barometric condenser condensate pump will trip

Reference:

ST-OP-315-0039 Response D HPCI will continue to operate in it's current configuration Incorrect because the barometric condenser condensate and vacuum pumps trip at 31 RPV level Author: CADDEN Keywords: HPCI Not Archived Date Last Used: LOCA Time: 2 2004 NRC RO Question Question ID: 35384 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 206000 K5.02 2.8 2.9  ; SRO ESP 206000 A3.05 4.3 4.3 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0039 INO Static

Question #32 Details EQ-OP-315-0140-000-C005-001 2004 RO NRC Exam Question Text During operation at 100% power a LOCA occurs and the following conditions exist :

RPV power...............................................0%, rods full in RPV pressure...............................................100 psig RPV water level....................+ 25 inches (slowly rising)

RHR System..................both divisions injecting to RPV Core Spray System........both divisions injecting to RPV An electrical fault in Core Spray Pump B motor windings causes the pump breaker to trip on overcurrent relays.

Given the above conditions, identify which one of the following actions are required by the operating crew.

Response A Throttle closed E2150-F005A to avoid pump runout on pump A.

Incorrect because no Division one pumps tripped Response B - Correct Answer Throttle closed E2150-F005B to avoid pump runout on pump D.

Reference:

23.203, precautions and limitations Response C Throttle open E2150-F005A to maintain division one flow >3175 gpm.

Incorrect because Division one flow should not have changed Response D Throttle open E2150-F005B to maintain division two flow >3175 gpm.

Incorrect because Division two flow can not achieve >3175gpm with only one pump Author: CADDEN Keywords: CSS Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35383 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 209001 A2.01 3.4 3.4  ; SRO ESP STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

23.203, precautions and limitations INO Static ST-OP-3115-0140

Question #33 Details EQ-OP-315-0114-000-A021-001 2004 RO NRC Exam Question Text SLC injection becomes necessary. The Operator places the initiation switch to PUMP A and the following occurs:

Squib continuity lights go out.

SLC Ignition Continuity Loss annunciator alarms.

SLC Pump A fails to start.

The operator places the initiation switch to PUMP B and SLC Pump B starts. Which one of the following actions should be taken NEXT?

Response A Attempt to start SLC Pump A a second time.

If the B pump is running, ther is no need to start the A pump.

Response B Direct an Operator to isolate SLC Pump A.

There is no need to isolate the pump if Pump B is running with no indication of a leak.

Response C Determine if the B explosive valve fired.

The only indication is the loss of continuity, then other indications such as power, tank level.

Response D - Correct Answer Check for indications of SLC flow to the RPV.

Reference ST-OP-315-0014 (1), (2)

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

Time: 2 Question ID: 35465 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 211000 A1.02 3.8 3.9  ; SRO ESP 211000 A4.08 4.2 4.2 STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0014 NOC  ; Close Ref.

INO Static

Question #34 Details EQ-OP-315-0127-000-A002-001 2004 RO NRC Exam Question Text Which one of the following statements describes the basis for automatic scrams associated with High Containment Pressure?

Response A to limit the fission product release from the fuel into containment Incorrect because this is the basis for the Hi Main Steam Line Radiation Scram Response B to counteract the pressure increase by rapidly reducing core power Incorrect because this is the basis for the Hi RPV Pressure Scram Response C to anticipate the rise in containment pressure and prevent exceeding the containment design pressure Incorrect because the Hi DW pressure scram is not based on containment pressure limits Response D - Correct Answer to minimize the possibility of fuel damage and to reduce the amount of energy being added to the coolant and the containment

Reference:

ST-OP-315-0127 Author: CADDEN Keywords: RPS Not Archived Date Last Used: CONTAINMENT Time: 2 2004 NRC RO Question Question ID: 35382 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 212000 K1.13 3.5 3.6  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0127 INO Static

Question #35 Details EQ-OP-315-0127-000-A018-006 2004 RO NRC Exam Question Text The plant was operating at 65% power when RPS Motor Generator Set "A" tripped.

Shortly after, a plant transient caused RPV level to drop to 165".

How will the RPS system respond to this event?

Response A - Correct Answer Full Reactor Scram

Reference:

ST-OP-315-0027(1), (2)

Response B Half Scram on RPS A Incorrect because RPS will get 1/2 Scram on A due to loss of power, and a full scram when level goes <L3.

Response C Half Scram RPS B Incorrect because RPS will get 1/2 Scram on A due to loss of power, and a full scram when level goes <L3.

Response D No SCRAM will occur Incorrect because RPS will get 1/2 Scram on A due to loss of power, and a full scram when level goes <L3.

Author: CADDEN Keywords: RPS Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35374 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 212000 K4.09 3.8 3.9  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0027 INO Static

Question #36 Details EQ-OP-315-0123-000-A011-001 2004 RO NRC Exam Question Text The RETRACT PERMIT light for IRM G is NOT lit. Which of the following describes the effect on IRM G?

Response A IRM will NOT retract.

Incorrect because the IRM will retract Response B - Correct Answer The IRM can be retracted. Retracting it will cause a Rod Block.

Reference:

ST-OP-315-0023 Response C The IRM can be retracted ONLY if IRM G is on Range 1. Retracting it will cause a Rod Block Incorrect because the IRM will retract on all ranges Response D The IRM can be retracted ONLY if IRM G is on Range 1. Retracting it will NOT cause a Rod Block.

Incorrect because the IRM will retract on all ranges and will cause a rod block Author: CADDEN Keywords: IRM Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35372 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 215003 K4.05 2.9 3.0  ; SRO ESP Generic 2.2.2 4.0 3.5 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0023 INO Static

Question #37 Details EQ-OP-315-0122-000-A013-002 2004 RO NRC Exam Question Text The plant was operating at 60% power when a loss of 24/48 VDC power occurred? How will this loss impact the plant?

Response A Main Turbine Trip Incorrect because MT trip logic powered from BOP battery Response B Loss of HPCI logic Incorrect because HPCI logic powered from ESF battery Response C - Correct Answer Loss of SRMs and IRMs

Reference:

ST-OP-315-0022 Response D Loss of Feedwater Level Control Incorrect because FW Level Control powered from UPS A Author: CADDEN Keywords: DC ELEC Not Archived Date Last Used: 2004 NRC RO Question Time: 3 SRM Question ID: 35369 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 215004 K6.02 3.1 3.3  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0064 INO Static ST-OP-315-0022

Question #38 Details EQ-OP-315-0024-000-A013-001 2004 RO NRC Exam Question Text The power supply for the APRMs is which one of the following?

Response A H11-P908A & B, 120 VAC instrument and control power.

Response B R3100S009A & B (UPS) Circuit 9.

Response C 2PA-1 and 2PB-1 via static inverters.

Response D - Correct Answer C71-P001A & B via QLVPS.

Reference:

ST OP-315-0024-001 (Table 2, PRNM Power Supplies)

This is a power supply question. The distractors are just wrong.

Author: BOLLINGER Keywords: PRNM Not Archived Date Last Used: APRM/OPRM Time: 2 Question ID: 33478 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 215005 K2.02 2.6 2.8 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST OP-315-0024-001 (Table 2, PRNM Power Supplies) INO Static

Question #39 Details EQ-OP-315-0143-000-A016-001 2004 RO NRC Exam Question Text The plant experienced a LOCA. RCIC is running and discharging to the RPV when 1D60, RCIC INVERTER FAILURE, alarms.

Which one of the following would describe (1) the impact on RCIC and (2) what actions must be taken?

Response A

1) Loss of indication on E51-R613, RCIC Pump Flow Indicator.

2) Manually control discharge flow using E51-F013, RCIC Pump Inboard Isolation Valve.

Incorrect because the correct action is to trip RCIC per ARP 1D60 Response B

1) Loss of indication on E51-K615, RCIC Discharge Flow Controller.

2) Manually control discharge flow using E51-F045, RCIC Turbine Steam Inlet Valve.

Incorrect because the correct action is to trip RCIC per ARP 1D60 Response C - Correct Answer

1) Loss of indication on E51-K615, RCIC Discharge Flow Controller.

2) Manually trip the RCIC turbine and supply the RPV with an alternate source.

Reference:

1D60 Response D

1) Automatic runback to minimum speed

2) Manually trip the RCIC turbine and supply the RPV with an alternate source.

Incorrect because there is no automatic runback feature to RCIC.

Author: BOLLINGER Keywords: RCIC Not Archived Date Last Used: _RO retake 2001 Time: 2 Question ID: 35389 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 217000 A2.10 3.1 3.1 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0043 INO Static 1D60

Question #40 Details EQ-OP-315-0142-000-A021-004 2004 RO NRC Exam Question Text A LOCA concurrent with a loss of offsite power has occurred and the following conditions exist :

RPV water level..................................42 inches (slowly lowering)

RPV pressure.................................................................670 psig Drywell pressure.................................................2.5 psig (rising)

EDGs 11 and 12..................................................... failed to start EDGs 13 and 14......................................tripped (will not restart)

Given the above conditions and assuming no ADS related operator actions are taken, how will the ADS system respond?

When the RPV water level drops below RPV Level-1, the 105-second timer will:

Response A Start, time out, then ADS will initiate.

Incorrect because the system does not meet the Low Pressure ECCS pump running permissive Response B - Correct Answer Start and time out but ADS will not initiate.

Correct because it will start due to the Hi DW and L1 signals, but not initiate because the low-pressure ECCS pump permissive will not be met (ADS Logic)

Response C NOT start and ADS will NOT initiate.

Incorrect because it will start based on L1 and Hi DW signals Response D Start after the 7 minute timer times out, then ADS will initiate.

Incorrect because the system does not meet the Low Pressure ECCS pump running permissive Author: BOLLINGER Keywords: ADS Not Archived Date Last Used: 2 _RO retake 2001 Time: 3 Question ID: 34823 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 218000 K5.01 3.8 3.8 SRO ESP 218000 K3.02 4.5 4.6 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0042 INO Static

Question #41 details EQ-OP-315-0105-000-B003-002 2004 RO NRC Exam Question Text How are open MSIVs affected when NSSS Isolation logic channels B and D trip, assuming logic channels A and C are NOT tripped?

Response A Inboard MSIVs, F022A-D close Response B All MSIVs close Response C Outboard MSIVs, F028A-D close Response D - Correct Answer All MSIVs remain open

Reference:

23.601, Enclosure G The justification for this answer is that MSIV isolation logic requires a one out two, taken twice logic to actuate. Since only division 2 logic is tripped, no isolation signal will be sent. The logic is half cocked.

Author: BOLLINGER Keywords: NUC BLR Not Archived Date Last Used:

Time: 3 Question ID: 25517 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 223002 A1.02 3.7 3.7 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0005-001 INO Static 23.601

Question #42 Details EQ-OP-315-0005-000-C005-001 2004 RO NRC Exam Question Text When controlling pressure using SRVs, it is expected SRVs for use will be selected based on the:

Response A SRV pressure setpoint Incorrect because only SRVs A and G have pressure control setpoints, otherwise they have safety pressure limits Response B - Correct Answer SRV position on the matrix

Reference:

23.201, Precautions and Limitations Response C Division of control air supplying drywell pneumatics Nitrogen supplies DW pneumatics when DW is inerted, only Division 1 control air can be aligned to DW pneumatics, normally when the DW is de-inerted.

Response D Main Steam Line to which they are attached Incorrect because it does not matter where the steam comes from.

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

Time: 1 Question ID: 30075 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 239002 K4.04 3.4 3.6 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

23.201, Precautions and Limitations INO Static

Question #43 Details EQ-OP-315-0171-000-C005-002 2004 RO NRC Exam Question Text The plant is experiencing a loss of Interruptible Air Supply (IAS). The following conditions exist:

Reactor power is 15%.

RPV water level is 200 inches and slowly rising.

Which one of the following is the cause of the rising RPV water level?

Response A Reactor Feed Pump Minimum Flow Valves starting to close.

These valves fail open on a loss of IAS Response B Heater Feed Pump Minimum Flow Valves starting to close.

This valve fails open on a loss of IAS Response C Reactor Feed Pump Discharge Valves to starting to open.

Neither valve is operated by IAS, and the valves are normally opened any way.

Response D - Correct Answer Startup Level Control Valve starting to open.

Reference:

ST-OP-315-0071, 20.129.01, Page 2 Author: CADDEN Keywords: COMPRESSED AIR Not Archived Date Last Used: 8/7/2000 2004 NRC RO Question Time: 0 Question ID: 35363 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 259002 K1.06 3.0 3.1  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0071 INO Static 20.129.01, Page 2

Question #44 Details EQ-OP-315-0146-000-A015-004 2004 RO NRC Exam Question Text The plant is operating at 100% power with the Feedwater Control System (FWCS) in 3 element control.

Which ONE of the following describes the response of the FWCS to a feed line rupture estimated at 5000 gpm in the A feedwater line?

FWCS will....

Response A - Correct Answer shift to single element control and raise the speed of both Reactor Feed Pump Turbines.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise the speed of the pumps.

Response B stay in three element control and raise the speed of the both Reactor Feed Pump Turbines.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise the speed of both pumps.

Response C shift to single element control and raise the speed of the A Reactor Feed Pump Turbine only.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise, not lower, the speed of both of the pumps.

Response D stay in three element control and raise the speed of the A Reactor Feed Pump Turbine only.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise the speed of both pumps.

Author: BOLLINGER Keywords: FEEDWATER CTRL Not Archived Date Last Used: FEEDWATER Time: 3 Question ID: 35441 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 259002 K6.05 3.5 3.5 SRO ESP 259002 A3.04 3.2 3.2 STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0064 NOC  ; Close Ref.

INO Static

Question #45 Details EQ-OP-315-0120-000-B006-001 2004 RO NRC Exam Question Text Following a Loss of Coolant Accident, the Standby Gas Treatment System has been in service for several hours venting the drywell and torus IAW 29.ESP.07, Primary Containment Venting. Chemistry reports that stack release rates have begun to rise.

Which of the following situations could explain the rise in release rates?

Response A SGTS total flow decrease to 2500 scfm Incorrect because less flow would not, by itself, cause release rates to rise.

Response B After Heater air temperature increase to 200°F Incorrect because the After Heater range is from 150-225°F.

Response C - Correct Answer Charcoal Adsorber temperature increase to 290°F.

Reference:

ST-OP-315-0020 Response D Moisture Separator differential pressure decrease to 0.4 inches water.

Incorrect because the Moisture Separator range is from 0-1 inches of water.

Author: CADDEN Keywords: SGTS Not Archived Date Last Used: 2004 NRC RO Question Time: 3 Question ID: 35362 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 261000 K1.07 3.1 3.2  ; SRO ESP 261000 K3,02 3.6 3.9 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0020 INO Static

Question #46 Details EQ-OP-315-0162-000-A006-001 2004 RO NRC Exam Question Text While the reactor was operating in Mode 1, a loss of offsite power occurred and the following conditions now exist:

Reactor power................................................0%, all rods fully inserted EDGs 11, 12 & 13...........................................failed to initiate EDG 14............................................operating and carrying its ESF Bus 480V AC Bus 72R..........................................energized What is the current status of the UPS system?

Response A Loads on Unit B are supplied from the UPS battery though the Inverter.

Incorrect because Loads are not being supplied from the battery Response B - Correct Answer Loads on Unit A are supplied from the Unit B Rectifier through the Unit A Inverter.

Reference:

ST-OP-315-0062-001(1), (2), Figure 2 Response C Loads on Unit A are supplied from its Alternate Source through the Static Transfer Switch.

Incorrect because Loads are not being supplied from the Alternate source Response D Loads on Unit B are supplied from its Alternate Source through the Static Transfer Switch.

Incorrect because Unit B Loads are being supplied from the Normal source Author: CADDEN Keywords: UPS Not Archived Date Last Used: 9/3/1997 2004 NRC RO Question Time: 1 Question ID: 35359 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 262002 K4.02 3.1 3.4  ; SRO ESP 262001 K3.04 3.1 3.4 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0062-001, Figure 2 INO Static

Question #47 Details EQ-OP-802-2003-000-S002-001 2004 RO NRC Exam Question Text The plant was operating at 25% power when Bus 65G was lost due to an electrical fault.

What action(s) is/are the Operating Crew required by AOP to perform immediately:

Response A - Correct Answer Place the Reactor Mode Switch to SHUTDOWN.

Reference:

20.138.01, Rev. 35 (Immediate Actions)

Response B Verify there are no thermal hydraulic instability oscillations.

Incorrect because the Immediate Action is to place the mode switch in S/D due to loss of both Recirc Pumps Response C Insert the Cram control rods and monitor for reactor core thermal hydraulic instabilities.

Incorrect because the Immediate Action is to place the mode switch in S/D due to loss of both Recirc Pumps Response D Raise reactor water level to raise natural circulation rate and commence inserting control rods.

Incorrect because the Immediate Action is to place the mode switch in S/D due to loss of both Recirc Pumps Author: CADDEN Keywords: AOP Not Archived Date Last Used: RRS Time: 1 2004 NRC RO Question Question ID: 35360 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.4.11 3.4 3.6  ; SRO ESP Generic 2.4.49 4.0 4.0 STAC Part A STAI Part B LOR Open Ref.

NOC  ; Close Ref INO Static

References:

20.138.01, Rev. 35 (Immediate Actions)

Question #48 Details EQ-OP-315-0145-000-B007-002 2004 RO NRC Exam Question Text The Turbine Building Rounds reported an acrid odor coming from UPS Distribution Panel A. The CRS decided to de-energize the panel. Which ONE of the following loads were affected?

Response A - Correct Answer Turbine Governor Control System

Reference:

ST-OP-315-0062 Response B 345Kv Mat Breaker Control Incorrect because it is powered from BOP DC Response C South RFPT Trip Relay Cabinet Incorrect because it is powered from BOP DC Response D RBHVAC Exhaust Fans Incorrect because powered from a Modular Power Unit Author: CADDEN Keywords: AOP Not Archived Date Last Used: RRS Time: 1 2004 NRC RO Question Question ID: 35360 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 262002 K1.05 2.7 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0062 INO Static

Question #49 Details EQ-OP-315-0164-000-C002-001 2004 RO NRC Exam Question Text What is the impact of a Loss of Division II ESF 130V/260V Battery on bus 72CF?

Response A Bus 72 CF will deenergize 72CF is an AC bus. It will not deenergize.

Response B There will be NO impact on bus 72CF 72CF will lose automatic throwover capability.

Response C - Correct Answer Automatic throwover capability for 72CF will be lost

Reference:

AOP 20.300.260ESF, Page 6 Response D Bus 72CF will automatically transfer to its alternate power supply Automatic throwover capability for 72CF will be lost Author: CADDEN Keywords: DC ELEC Not Archived Date Last Used: 2004 NRC RO Question Time: 3 Question ID: 35345 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO G2.4.11 3.4 3.6  ; SRO ESP 263000 K4.01 3.1 3.4 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

AOP 20.300.260ESF INO Static

Question #50 Details EQ-OP-315-0165-000-A021-005 2004 RO NRC Exam 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 on a loss of power 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-315-0065 Response D The EDG will automatically start. The loads on bus 64B will NOT sequence after the output breaker is closed.

Anytime the output breaker closes, and the sequencer has not been reset, the loads will sequence on.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35558 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 264000 A3.05 3.4 3.5 SRO ESP STAC Part A STAI Part B

References:

LOR Open Ref.

ST-OP-315-0065 NOC  ; Close Ref.

INO Static

Question #51 Details EQ-OP-315-0171-000-A014-001 2004 RO NRC Exam Question Text The plant is operating at 100% power with the following auxiliary equipment lineup:

West Station Air Compressor running; Center in AUTO South Reactor Feedwater Pump Turbine East Lube Oil Pump running; West in AUTO North Reactor Feedwater Pump Turbine West Lube Oil Pump running; East in AUTO North Main Turbine Lube Oil Pump running; South in AUTO South and Center TBCCW pumps running Bus 72 A is lost due to an internal electrical fault. What is your response to this event?

Response A Perform a rapid power reduction Incorrect because Loss of 64A says put the mode switch in Shutdown Response B Start both SBFW pumps and inject at 1200 gpm Incorrect because the RFPT Emergency LO Pumps are sufficient to supply the RFPTs, therefore RFPs will not trip.

Response C Verify the North TBCCW pump has started automatically Incorrect because 64A is the power supply to N. TBCCW pump Response D - Correct Answer Verify the Center Station Air Compressor has automatically started

Reference:

ST-OP-315-0171-001, 20.300.64A Page 5 Author: CADDEN Keywords: 4160/480 ELEC Not Archived Date Last Used: COMPRESSED AIR Time: 5 2004 NRC RO Question Question ID: 35341 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 300000 K2.01 2.8  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

20.300.64A INO Static ST-OP-315-0171-001 6SD721-2500-01

Question #52 with Details EQ-OP-315-0171-000-A016-001 2004 RO NRC Exam Question Text The plant is operating at 85% power when maintenance activities resulted in an inadvertent transfer of MPU-3. Which of the following is the expected plant response with no operator action?

Response A - Correct Answer Outboard MSIVs will go shut

Reference:

20.129.01 Page 2 and 8 Response B TBCCW TCV will remain in its current position Incorrect because the valve will fail OPEN Response C Condensate Polishing Demineralizers effluent valves will go full open Incorrect because the valve is supplied by Station Air Response D LP Hood Spray pressure and temperature control valves will go shut Incorrect because the valves will fail OPEN Author: CADDEN Keywords: COMPRESSED AIR Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35340 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 300000 K6.07 2.5 2.6  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

INO Static 20.129.01 Page 2 and 8

Question #53 Details EQ-OP-315-0167-000-B003-003 2004 RO NRC Exam Question Text Concerning the RBCCW/EECW System, which ONE of the following describes the SEQUENCE of events that will occur when there is a Loss of Off-Site Power (LOP)?

Response A - Correct Answer White Emergency Mode Light comes on, EDG Output Breakers close, Supply and Return Header Isolation Valves close, EECW Pumps start.

Reference:

ST-OP-315-0067-001, (2)

Response B RBCCW Pumps trip, EDG Output Breakers close, EECW Make-Up Tank Isolation Valves close, EECW Pumps start.

Incorrect because the EECW Make-up tank isolation valve OPENS Response C White Emergency Mode Light comes on, EECW Make-Up Tank Isolation Valves open, EDG Output Breakers close, EECW Pumps start.

Incorrect because the EDG output breakers close before the make-up tank isolation opens Response D RBCCW Pumps trip, Supply and Return Header Isolation Valves close, EDG Output Breakers close, EECW Pumps start.

Incorrect because the EDG output breakers close before the Supply and Return Isolation valves close Author: CADDEN Keywords: RBCCW/EECW Not Archived Date Last Used:

Time: 3 Question ID: 34534 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 400000 A4.01 3.1 3.0 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0067-001 INO Static

Question #54 Details EQ-OP-802-2001-000-R003-002 2004 RO NRC Exam Question Text During an ATWS event, the following conditions exist:

FSQ 1 through 8...............................................................................Complete 8 Blue RPS lights.................................................................................ON 3D6, SCRAM VALVE PILOT AIR HDR PRESS HIGH/LOW........OFF All rods are full out.

Given these conditions, which of the following describes (1) the plant condition, and (2) the method(s) for control rod insertion.

Response A - Correct Answer (1) Scram pilot air valves are energized.

(2) Deenergize the scram solenoids.

Reference:

ST-OP-315-0010-001 Response B (1) Backup scram pilot air valves are deenergized.

(2) Perform 29.ESP.09, DEFEAT OF RPS AUTOMATIC LOGIC TRIPS, AND perform Scram Reset Scram.

Backup scram air valves are deenergized. 29.ESP.09 is not required because RPS did not actuate.

Response C (1) ARI valves are deenergized.

(2) Perform 29.ESP.10, DEFEAT OF ARI LOGIC TRIPS, AND perform Scram Reset Scram.

ARI valves are normally deenergized, and based on 3D6, still are. Therefore 29.ESP.10 would not be necessary.

Response D (1) ARI valves are energized.

(2) Open scram switches.

Based on the conditions, ARI valves are not energized, opening scram switches is normally done when only a few rods are stuck.

Author: CADDEN Keywords: CRDH Archived Date Last Used: AOP Time: 3 Question ID: 32645 Points: 1 Parent ID: 30789 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 201001 A2.01 3.2 3.3 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

20.106.01 INO Static ST-OP-315-0010-001

Question #55 Details EQ-OP-315-0109-000-C011-002 2004 RO NRC Exam Question Text During a plant startup, Control Rod 26-35 was withdrawn to position 48. During the coupling check:

Position indication was lost 3D76 CONTROL ROD OVERTRAVEL alarmed 3D80 CONTROL ROD DRIFT alarmed (1) What is the status of Control Rod 26-35 and (2) what procedure should the Control Room Staff enter and execute?

Response A (1) stuck (2) AOP 20.106.05 STUCK CONTROL ROD Incorrect because these are indications of an uncoupled control rod Response B (1) uncoupled (2) AOP 20.106.1 CRD HYDRAULIC SYSTEM FAILURE.

Incorrect because the crew should enter 20.106.02 Response C - Correct Answer (1) uncoupled (2) AOP 20.106.02 UNCOUPLED/DROPPED CONTROL ROD (FROM REACTOR CORE)

Reference:

20.106.02, page 7 Response D (1) stuck (2) SOP 23.106 CONTROL ROD DRIVE HYDRAULIC SYSTEM, difficult rod movement section.

Incorrect because these are indications of an uncoupled control rod Author: CADDEN Keywords: CRDM Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35339 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 201003 A2.02 3.7 3.8  ; SRO ESP 201003 A4.02 3.5 3.5 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

20.106.02, page 7 INO Static

Question #56 Details EQ-OP-315-0104-000-A013-002 2004 RO NRC Exam Question Text The "A" Reactor Recirc Pump has been given a signal to increase speed. What is occurring in the fluid drive coupling?

The scoop tube positioner is changing position to _________ the amount of oil in the working circuit of the coupler thus _________ the coupling between the Reactor Recirc Motor and Generator.

Response A reduce, reducing Incorrect because this will be the case when lower speed is desired Response B reduce, increasing Incorrect because less oil in the working speed will lower the coupling Response C increase, reducing Incorrect because increasing the amount of oil will increase the coupling Response D - Correct Answer increase, increasing

Reference:

ST-OP-315-0004-001 Author: PRE-EXISTING Keywords: RRS Not Archived Date Last Used: 3/16/2001 Time: 2 Question ID: 33031 Points: 1 Parent ID: 25453 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 202001 K1.12 3.6 3.6 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0004-001 INO Static

Question #57 Details EQ-OP-315-0111-000-A013-002 2004 RO NRC Exam Question Text A reactor startup is in progress with the following conditions:

Rod Select Power Switch........................................ON Select button for rod 26-31......................................ON 3D80, Control Rod Drift...........................................ON What is the cause of the Control Rod Drift Alarm?

Rod 26-31 at position..

Response A - Correct Answer 35 with the Rod Control Movement Switch in OFF

Reference:

ST-OP-315-011 Response B 35 with the Rod Control Movement Switch in OUT NOTCH Incorrect because RMCS still thinks the rod is moving Response C 34 with the Rod Control Movement Switch in OFF there will be no rod drift if the rod settles on an even position Response D 34 with the Rod Control Movement Switch in OUT NOTCH Incorrect because RMCS still thinks the rod is moving and there will be no rod drift if the rod settles on an even position Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35393 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 214000 K4.01 3.0 3.1 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-011 INO Static

Question #58 Details EQ-OP-315-0141-000-A021-009 2004 RO NRC Exam Question Text Division 1 of RHR was operating in torus cooling mode with "A" RHR pump in service to support an upcoming HPCI surveillance. The plant experienced a seismic event, which resulted in a failure to SCRAM and a LOCA. The following conditions exist:

RPV Level................................-10" on Core Level Reactor Power.............................0%

RPV Pressure..............................650 psig Drywell Pressure........................ 12 psig Torus Pressure.............................10.2 psig (1) How would RHR respond to this event, and (2) What minimum operator action is necessary to realign RHR Pump "A" back to torus cooling?

Response A (1) Division 1 RHR will continue to operate in Torus Cooling.

No action required.

Incorrect because RHR Torus cooling will isolate on Hi Drywell Pressure and L1 Response B (1) E11-F024A, Div 1 RHR Torus Clg Iso.and E11-F028A, Div 1 RHR Torus Iso Vlv. will automatically close.

(2) Place Containment Spray Mode Select switch in MANUAL, and reopen the E11-F024A and E11-F028A valves.

Incorrect because must use 2/3 Core Height Override due to Level <0 Response C - Correct Answer (1) E11-F024A, Div 1 RHR Torus Clg Iso. and E11-F028A, Div 1 RHR Torus Iso Vlv. will automatically close.

(2) Place Containment Spray Mode Select switch in MANUAL and Containment Spray 2/3 Core Height Override keylock switch in MANUAL OVERRIDE and reopen the E11-F024A and E11-F028A valves.

Reference:

ST-OP-315-0041(1). (2); 23.205, page 103 Response D (1) E11-F024A, Div 1 RHR Torus Clg Iso. will automatically close.

(2) Place Containment Spray Mode Select switch in MANUAL and Containment Spray 2/3 Core Height Override keylock switch in MANUAL OVERRIDE and reopen the E11-F024A valve.

Incorrect because E11-F028A will also close and will need to be reopened.

Author: CADDEN Keywords: RHR - TOR CLNG Not Archived Date Last Used: RHR - LPCI Time: 5 RHR - GENERAL Question ID: 35338 Points: 1 2004 NRC RO Question Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 219000 A4.06 3.9 3.7  ; SRO ESP 219000 A1.02 3.5 3.5 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

23.205, page 103 INO Static ST-OP-315-0041

Question #59 Details EQ-OP-315-0116-000-A021-002 2004 RO NRC Exam Question Text During a Design Bases Loss of Coolant Accident the Drywell Spray Mode of RHR is initiated. How will the Containment System respond?

Response A - Correct Answer Suppression Chamber to Drywell Vacuum Breakers will open to ensure Drywell to Torus d/p is maintained within limits.

Reference:

ST-OP-315-0016(1), (2)

Response B Suppression Chamber to Drywell Vacuum Breakers will open to ensure Drywell pressure is maintained lower than Torus pressure.

The vacuum breakers prevent damage to the containment from d/p. DW pressure is usually higher than torus pressure.

Response C Reactor Building to Suppression Chamber Vacuum Breakers will open to ensure Reactor Building to Torus d/p is maintained within limits.

The RB Vacuum breakers are for inadvertent initiation of Torus Sprays.

Response D Reactor Building to Suppression Chamber Vacuum Breakers will open to ensure Torus pressure is maintained higher Reactor Building Pressure.

Right reason, but wrong cause. RB Vacuum breakers not for DW sprays after a DBA LOCA.

Author: CADDEN Keywords: CONTAINMENT Not Archived Date Last Used:

Time: 3 Question ID: 35337 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 226001 A1.01 3.6 3.8  ; SRO ESP 226001 K5.06 2.6 2.8 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0016 INO Static

Question #60 Details EQ-OP-315-0105-000-A021-003 2004 RO NRC Exam Question Text The plant was operating at 85% power when Main Steam was lost to the West Moisture Separator Reheater. Which of the following describes the effect of this loss?

Loss of Main Steam to the Moisture Separator Reheater would cause the:

Response A HP Turbine to experience a significant increase in windage losses and become less efficient The HP turbine is upstream of the MSR, therefore there is no effect.

Response B - Correct Answer LP Turbines to experience more damage to the first stage blading and to become less efficient

Reference:

ST-OP-315-0005 Response C LP Turbines to lose approximately half their steam flow and scram the Rx on closure of the LP Stop and Intercept valves The LP turbines will not lose all of their steam flow and the Rx will not scram.

Response D HP Turbine to pick up more load and therefore the thrust on the HP Turbine would be above its Maximum Normal Range.

The HP turbine is upstream of the MSR, therefore there is no effect.

Author: CADDEN Keywords: NUC BLR Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35336 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 239001 K1.05 2.8 2.8  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0005 INO Static

Question #61 Details EQ-OP-315-0107-000-B007-002 2004 RO NRC Exam Question Text The plant was operating steady state at 100% power when the South RFP tripped.

Which of the following describes the expected plant response?

(Assume no operator action).

Response A - Correct Answer RPV level - Lowers, then stabilizes Recirc speed - Lowers Rx Power - Lowers

Reference:

ST-OP-315-007 Response B RPV level - Lowers Recirc speed - Lowers Rx Power - 0% (SCRAM)

Incorrect because the Reactor will not SCRAM on Level 3 Response C RPV level - Lowers Recirc speed - Raises Rx Power - Steady Incorrect because the Recirc pumps will run back on limiter #2 Response D RPV level - Lowers, then stabilizes Recirc speed - Steady Rx Power - Lowers Incorrect because Recirc pumps will run back on limiter #2 Author: CADDEN Keywords: RX FEEDWATER Not Archived Date Last Used:

Time: 3 Question ID: 35334 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 259001 K3.01 3.9 3.9  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-007 INO Static

Question #62 Details EQ-OP-315-0135-000-A021-001 2004 RO NRC Exam Question Text The plant is operating at 75% power. The Dilution Steam controller for the operating off-gas train fails and admits 100% dilution steam to the 18" manifold.

Select from below the expected off-gas system response:

Response A Total off-gas flow will decrease Incorrect because total off gas flow will increase due to increased steam supply Response B Hydrogen concentration will increase Incorrect because hydrogen concentration will decrease due to increased steam supply (recombining of O2/H2 into water vapor)

Response C Off-gas after cooler temperature will increase Incorrect because after cooler will decrease due to lowered recombiner outlet temperature Response D - Correct Answer Thermal recombiner outlet temperature will decrease

Reference:

ST-OP-315-0035-001 Author: CADDEN Keywords: OFF GAS Not Archived Date Last Used:

Time: 2 Question ID: 35333 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 271000 K6.04 2.8 2.8  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0035-001 INO Static

Question #63 Details EQ-OP-315-0172-000-B003-002 2004 RO NRC Exam Question Text The following conditions exist:

7D6, DIESEL FIRE PUMP AUTO START................................ON 7D11, ELECTRIC FIRE PUMP AUTO START.........................OFF CMC Switch for the diesel fire pump.......................................AUTO CMC Switch for the electric fire pump........................................AUTO Diesel Fire Pump..........................................................................running Electric Fire Pump........................................................................not running No operator actions have been taken.

What condition would cause these indications?

Response A - Correct Answer Loss of AC control power to the Diesel Fire Pump.

Reference:

ST-OP-315-0072 Response B Fire header pressure of 130 psig.

This is the pressure the Electric Fire Pump (EFP) would auto start, the Diesel Fire Pump (DFP) auto starts at 110 psig.

Response C GSW pressure of 80 psig.

There is a manual cross connection to GSW, and the jockey pumps are supplied by GSW, there is no auto action based on GSW pressure.

Response D Fire header jockey pump tripped.

If a jockey pump tripped, its possible that fire header pressure could lower, leading to the eventual start of the EFP and then the DFP.

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

Time: 0 Question ID: 35549 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 286000 A3.01 3.4 3.4  ; SRO ESP STAC Part A

References:

STAI Part B ST-OP-315-0072 LOR Open Ref.

NOC  ; Close Ref.

INO Static

Question #64 Details EQ-OP-315-0173-000-B001-001 2004 RO NRC Exam Question Text Division I CCHVAC was operating in Purge mode due to a fire in the Relay Room.

Annunciator 3D35, DIV I/II FP VENT EXH RADN MONITOR UPSCALE TRIP, alarms due to high radiation in the Fuel Pool exhaust. What will happen to the CCHVAC configuration?

Div I CCHVAC will:

Response A continue to operate in Purge mode.

Incorrect because recirculation mode overrides all other modes.

Response B - Correct Answer transfer from Purge mode to Recirculation mode.

Reference:

ST-OP-315-0073-001 (1), (2), ARP 3D35 Response C trip and will have to be started manually in Recirculation mode.

Incorrect because CCHVAC will automatically shift to recirculation mode Response D trip and Div II CCHVAC will start and operate in Recirculation mode.

Incorrect because CCHVAC will automatically shift to recirculation mode Author: CADDEN Keywords: CCHVAC Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35326 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 290003 K4.01 3.1 3.2  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0073-001 INO Static ARP 3D35

Question #65 Details EQ-OP-315-0103-000-A007-002 2004 RO NRC Exam Question Text Which of the following are two advantages of loading burnable poisons into the fuel?

Response A Radial power shaping and allow lower power fuel bundles to be used.

Incorrect because water rods help with radial power shaping. Reference Response B Longer control rod life and smoother reactivity control.

Incorrect. This is a description of using a control cell core Reference Response C - Correct Answer Longer fuel cycles and axial power shaping.

Reference:

ST-OP-315-0003-001 Response D Wider margin to thermal limits and allow lower power fuel bundles to be used.

Incorrect. This is a description of using a ring of fire. Reference Author: CADDEN Keywords: CORE & FUEL Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35324 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 234000 G2.1.28 3.2 3.3  ; SRO ESP 290002 K5.03 2.7 3.0 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0003 INO Static

Question #66 Details EQ-OP-213-0041-000-B001-006 2004 RO NRC Exam Question Text In accordance with MOP09, "Locked Valve", a ____________________ padlock should be used on a locked closed position valve.

Response A Red Incorrect because red is open Response B Green Incorrect because green is not used for padlock locked valves Response C red with black dot Incorrect because red with black dot is throttled Response D - Correct Answer no color identification

Reference:

MOP09, section 3.8 Author: BOLLINGER Keywords: ADMIN Archived Date Last Used:

Time: 2 Question ID: 32576 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.1.1 3.7 3.8 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

MOP09 INO Static

Question #67 Details EQ-OP-315-0104-000-C011-001 2004 RO NRC Exam Question Text The plant was operating at 95% power when the following indications were observed:

Generator megawatt output - 1095MWe, lowering slowly Reactor power - 88%, lowering slowly RPV level - 197 inches, steady RPV pressure - 1015 psig, lowering slowly Total core flow lowered and stabilized at 83 Mlbm/hr A Recirc System: B Recirc System:

recirc loop flow - 55000 gpm recirc loop flow - 40000 gpm jet pump loop flow - 22 Mlbm/hr jet pump loop flow - 61 Mlbm/hr Based on the given conditions what action should be taken?

The Shift will enter Response A 20.000.21, Reactor Scram Incorrect because indications are of a jet pump failure. You would commence a plant shutdown, not scram.

Response B 20.138.01, Recirculation Pump Trip Incorrect because these are the actions for uncontrolled recirc flow change.

Response C 20.138.03, Uncontrolled Recirc Flow Change Incorrect because there is no indication that RRS MG speed has changed.

Response D - Correct Answer 20.138.02, Jet Pump Failure

Reference:

20.138.02, page 5 Author: DOUCET Keywords: RRS Not Archived Date Last Used: 8/27/2002 _RO retake 2001 Time: 2 Question ID: 34691 Points: 1 Parent ID: 33560 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO generic 2.1.7 3.7 4.4 SRO ESP STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

ST-OP-315-0004 INO Static 20.138.02

Question #68 Details EQ-OP-315-0110-000-A008-001 2004 RO NRC Exam Question Text The plant is in Mode 4 with Control Rod Drive Pump A operating in conjunction with Reactor Water Cleanup to maintain water level at 255 inches. The last running Condensate Pump is shutdown. How will the CRD Hydraulic system respond?

Response A CRD Pump A trips on Low suction Pressure.

Plausible that a loss of suction would cause a pump trip, although the suction is not actually lost.

Response B Demin Water Pumps auto start to supply CRD Pump A.

Plausible because backup supply comes from the Condensate Storage Tank, which is tied to Demin water.

Response C Torus Water Management Pumps auto start to supply CRD Pump A.

Plausible because normal supply to the CRD pump also is the normal supply to the TWMS makeup Response D - Correct Answer CRD Pump A suction supply transfers to the Condensate Storage Tank.

Reference:

ST-OP-315-0010 Author: CADDEN Keywords: CIRC WATER Not Archived Date Last Used:

Time: 3 Question ID: 35395 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.1.27 2.8 2.9  ; SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

INO Static

Question #69 Details EQ-OP-802-4101-000-0022-008 2004 RO NRC Exam Question Text Which one of the following is required when a non-visible break must be used to disconnect a piece of equipment from its power supply?

Response A Independent verification of the caution tag.

Incorrect because you would not use a caution tag for personal protection.

Response B An approved grounding device installed on the load side.

Incorrect because you may or may not use a grounding device, depending on the load.

Response C - Correct Answer An approved blocking device and a method for determining that power is removed.

Reference:

MOP12, section 3.2.11 Response D A safety observer is stationed for all work performed on the equipment.

Incorrect because the work will be considered deenergized, therefor no safety observer required.

Also, safety observers may be used at the Operating Authorities discretion.

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

Time: 3 Question ID: 34573 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.2.13 3.6 3.8 SRO ESP STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

MOP12 INO Static

Question #70 Details EQ-OP-315-0190-000-C005-004 2004 RO NRC Exam Question Text Refueling is in progress. As a once burned fuel bundle is being placed in the core SRM counts on one of the 2 operable SRM detectors begin increasing with a steady positive period. In accordance with procedure MOP13, Refueling Operations, as the Reactor Operator, you IMMEDIATELY:

Response A direct the refuel floor to evacuate.

Incorrect because you would evacuate based on hi monitored radiation levels Response B - Correct Answer direct the refuel floor to stop fuel movement.

Reference:

MOP13, section 3.3 Response C inform the refuel floor to remove the fuel bundle and try again.

Incorrect because the RO would not direct the refuel floor to do anything. SRO job.

Response D declare the improperly responding SRM INOP and insert all insertable control rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Incorrect because MOP13 states you should believe all instrument indications (section 3.3.1)

Author: BARRETT Keywords: Not Archived Date Last Used: 2/7/2000 Time: 0 Question ID: 34502 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.2.30 3.5 3.3 SRO ESP 295023 K1.03 3.7 4.0 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

MOP13, Conduct of Refueling and Core Alterations INO Static

Question #71 Details EQ-OP-802-4101-000-0022-007 2004 RO NRC Exam Question Text An operator is conducting a normal day to day rounds inspection of equipment which is located in a high radiation area. In accordance with MOP04, Shift Operations, and MRP05 , ALARA/RWPs, the operator must:

Response A preplan the inspection during turnover.

Not in accordance with the references Response B - Correct Answer conduct the inspection from the barrier to the area.

Reference : MRP05, MOP4 Response C obtain Radiation Protection supervisor approval.

Not in accordance with the references Response D enter the area with a hand held monitoring device.

Not in accordance with the references Author: BOLLINGER Keywords: ADMIN Not Archived Date Last Used:

Time: 3 Question ID: 35422 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.3.2 2.5 2.9  ; SRO ESP STAC Part A

References:

STAI Part B MOP4 LOR Open Ref.

MRP05 NOC  ; Close Ref.

INO Static

Question #72 Details EQ-OP-508-0001-000-A013-004 2004 RO NRC Exam Question Text A fully qualified Radiation Worker was escorting a male visitor with no previous exposure through the Reactor Building when they inadvertently walked through a high radiation area. Assuming no previous exposure, RP personnel read the dosimeters for the individuals and calculated that they received the following radiation exposure:

Chest 800 mrem Hands 1060 mrem Eye Lens 510 mrem Internal 550 mrem Which, if any, exposure limit has been exceeded?

Response A Both exceeded Federal TEDE limits.

Incorrect because the fully qualified Radiation Worker did not exceed Federal TEDE limits Response B Both exceeded Fermi administrative TEDE limits.

Incorrect because the fully qualified Radiation Worker did not exceed Fermi TEDE limits Response C - Correct Answer Only the male visitor exceeded the federal TEDE limit

Reference:

ST-GN-508 Response D Only the fully qualified Radiation Worker exceeded the federal TEDE limit Incorrect because the fully qualified Radiation Worker did not exceed Federal TEDE limits Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: ADMIN Time: 2 Question ID: 35322 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO generic 2.3.4 2.5 3.1  ; SRO ESP STAC Part A

References:

STAI Part B 10 CFR 20 LOR Open Ref.

ST-GN-508 NOC  ; Close Ref.

INO Static

Question #73 Details EQ-OP-802-2001-000-R009-001 2004 RO NRC Exam Question Text When does ODE-03, Communications, allow relaxing of the 3-way communications requirement?

Response A When communicating face-to-face during peer checks Incorrect because 3-way communications are expected to be used during peer checks.

Response B When transferring information important to plant safety to the CRS.

Incorrect because 3-way communications are expected to be used when transferring plant information.

Response C - Correct Answer During transients when the CRS requests frequent updates of a certain parameter.

Reference:

ODE-03, Communications, page 2 Response D During testing evolutions between the Control Room Operator and the technician in the field.

Incorrect because 3-way communications are expected to be used during testing and maintenance activities.

Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: ADMIN Time: 2 Human Performance Question ID: 35319 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.4.15 3.0 3.5  ; SRO ESP STAC Part A

References:

STAI Part B ODE-03, Communications LOR Open Ref.

MOP03  ; NOC Close Ref.

INO Static

Question #74 Details EQ-OP-802-4101-000-0028-006 2004 RO NRC Exam Question Text In accordance with MOP10, "Fire Brigade", which one of the following individuals could be assigned to the fire brigade with the plant operating in mode one?

Assume each individual has met the physical and training requirements.

Response A Reactor Operator - assigned as Safe Shutdown Incorrect because required to be available for Safe Shutdown Response B Radwaste Operator -assigned as shift communicator Incorrect because required to be available to act as shift communicator Response C Senior Reactor Operator - assigned as the shift manager Incorrect because required to be available to act as Shift Manager Response D - Correct Answer Nuclear Operator - assigned as Turbine Building Rounds

Reference:

MOP 10, section 3.1 Author: CADDEN Keywords: FIRE PROT/DET Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35318 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO 286000 2.4.26 2.9 3.3 SRO ESP Generic 2.4.25 2.9 3.4 STAC Part A STAI Part B

References:

LOR Open Ref.

MOP10 NOC  ; Close Ref.

INO Static

Question #75 Details EQ-OP-802-2004-000-0001-008 2004 RO NRC Exam Question Text During a reactor startup the following conditions exist :

RPV Pressure.................................................680 psig RPV water level...........................................193 inches RWCU System.....................in Blowdown Mode If the operating CRD Pump trips followed by Annunciator 3D10,CRD ACCUMULATOR TROUBLE (in alarm for one withdrawn rod), the Operating Crew is required by AOP to immediately:

Response A Start the standby CRD pump.

Incorrect because pressure is <900 psig and 3D10 in alarm for a withdrawn control rod Response B - Correct Answer Place the Reactor Mode Switch to SHUTDOWN.

Reference:

20.106.01, (Immediate Actions)

Response C Have a Nuclear Operator check the local alarm panel.

Incorrect because the reactor must be scrammed and then a lot of alarms will come in on the local control panel.

Response D Monitor for the second control rod DRIFT alarm to activate, then manually scram the reactor.

Incorrect because this is the immediate actions for Control Rod drift. There are no drifting control rods given in the stem.

Author: BOLLINGER Keywords: AOP Archived Date Last Used: CRDH Time: 1 LOR 00-04 Question ID: 30908 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value  ; RO  ; ILO Generic 2.4.11 3.4 3.6 SRO ESP Generic 2.4.49 4.0 4.0 STAC Part A STAI Part B LOR Open Ref.

References:

NOC  ; Close Ref.

20.106.01, (Immediate Actions) INO Static