Text

Initial Submittal of the Written Exam for the Quad Cities Initial Examination - June 2007
	ML072920420
Person / Time
Site:	Quad Cities
Issue date:	10/18/2007
From:	; NRC/RGN-III/DRS/OLB
To:	; Exelon Generation Co, Exelon Nuclear
References
	50-254/07-301, 50-265/07-301 50-254/07-301, 50-265/07-301
	Download: ML072920420 (104)
	v • d • e

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KA 295001K201

QUESTION Unit 1 is at 80%. All condensate/booster pumps and feedwater pumps are in operation. The Unit 1 NSO observes the following conditions:

- a decrease in power level as indicated on APRMs.

- a decrease in B loop recirculation flow.

- a decrease in feedwater flow.

These conditions were most likely due to . . .

a. a loss of feedwater heating.

b. de-energization of bus 12.

c. the trip of a condensate booster pump.

d. a spurious actuation of ATWS circuitry.

ANSWER b.

REFERENCE QCAN 901-6, F-7, Reactor feed Pump Auto Trip annunciator, Rev. 11 Lesson Plan 3200, Feedwater Lesson Plan 0202, Recirculation System NEW HIGHER

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KA 295003A102

QUESTION Both Units have experienced a station blackout. Both SBO diesels have been started. Local operations have resulted in a successful start of the U1 EDG.

In order to parallel and transfer electrical loads FROM the Unit 1 SBO to the Unit 1 EDG, what would be the required positions of the ISOCH/DROOP settings on the U1 SBO and the SPEED DROOP knob on the U1 EDG?

SBO DG ISOCH/DROOP EDG DROOP KNOB setting

a. DROOP 0

b. ISOCHRONOUS 50

c. DROOP 50

d. ISOCHRONOUS 0

ANSWER b

REFERENCE Lesson Plan 6620, SBO System QCOP 6620-14 Attachment A NEW HIGHER

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KA 295004K302

QUESTION The DC System engineer has confirmed that voltage on the 250 VDC Safety Related bus has lowered to 230 VDC due to a hard ground.

This ground is classified as a ___(1)____ and the actions to be taken include: ___(2)___ .

(1) (2)

a. Level I ground NO immediate actions required, record condition each shift.

b. Level II ground immediately locate and isolate the ground, do NOT enter a time clock.

c. Level II ground initiate a 7-day clock to locate, isolate and repair the ground.

d. Level III ground initiate a 14-day clock to locate, isolate and repair the ground.

ANSWER b.

REFERENCE Lesson Plan 6900, DC Distribution QOP 6900-04, 250 VDC Ground Detection Unit 1, Rev17 NEW HIGHER

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KA 295005A208

QUESTION The Unit Supervisor ordered the Unit 1 reactor to be scrammed due to drifting Control Rods.

Post trip conditions are normal.

In accordance with QCGP 2-3, Reactor Scram procedure, the NSO will VERIFY ALL of the following regarding the electrical distribution system status after the turbine generator trips EXCEPT:

a. Load shed relay on Bus 11 and Bus 12 has picked up.

b. Both 345 KV OCB circuit breakers 6-7 and 7-8 are open.

c. Aux Power has transferred.

d. Main Generator Exciter Field breaker is open.

ANSWER a.

REFERENCE QCGP 2-3, Reactor Scram, Rev 58.

NEW FUNDAMENTAL

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KA 295006 2.4.1

QUESTION A transient has occurred that resulted in the Unit 2 NSO scramming the reactor. The following post-trip conditions exist:

- Reactor power is range 8 on IRMs and lowering

- CRDs A-6 and A-10 are at position 04

- Drywell pressure is 2.1 psig and rising slowly

- Drywell temperature is 175 degrees F and rising slowly

- Reactor water level dropped to +4 inches and is rising slowly

- Torus temperature is 98 degrees F and rising slowly The NSO recommends to the Unit Supervisor to enter _____(1)__________

because _____(2)________ exceeds the QGA Entry Condition.

(1) (2)

a. QGA 100, RPV Control RPV Water

b. QGA 100, RPV Control Reactor Power

c. QGA 200, Primary Containment Control Drywell Temperature

d. QGA 200, Primary Containment Control Torus Temperature

ANSWER d.

REFERENCE QGA 100, RPV Control, Rev 8 April 2006 QGA 200, Primary Containment Control, Rev 8, Feb 2002 295006 2.4.1 NEW HIGHER

QNUM 006

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QDATE 2007/06/04

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KA 295016.K2.03

QUESTION Unit 1 has been shutdown for a month for a refuel outage. Unit 2 has been shutdown for a week for a forced outage. The B Control Room ventilation system is operating for testing.

Maintenance personnel inadvertently spilled a barrel of sulfuric acid in the Auxiliary Electric Equipment room and notified the Control Room that personnel received skin burns from the fumes and have left the area. The Shift Manager ordered the Control Room abandoned and had B CR HVAC system secured.

Securing the B HVAC limits the forced circulation of fumes through each of the following areas except the . . .

a. Cable Spreading Room.

b. Old Computer Room.

c. 3rd Floor Service Building.

d. B Control Room HVAC Equipment Room.

ANSWER c.

REFERENCE Lesson Plan 5752, Control Room Ventilation System, pgs 4-8 NEW FUNDAMENTAL

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KA 295018K101

QUESTION Both units are at full power operation. With the Mississippi river water temperatures about 85 degrees F and constant, the Unit 1 NLO reports a rising trend in the temperatures of various heat exchangers that discharge service water to the King Hole. Temperatures of systems serviced by the Queen Hole are steady. Believing that there may be blockage in the U1 King Hole, the Operators would expect to see which ONE of the following?

a. Drywell pressure rising.

b. SSMP room temperature rising.

c. Service water header pressure lowering.

d. Main generator stator temperature rising.

ANSWER a.

REFERENCE P&ID 22, Service Water System NEW HIGHER

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KA 295019K301

QUESTION With Unit 1 instrument air system in its normal lineup, what actuations/alarms occur in order as system air pressure lowers:

a. Unit 1A Instrument Air Low Pressure Alarms, Unit 1A Dryer Bypass Valve Opens, 1A Service Air Backup Valve Opens.

b. 1A Service Air Backup Valve Opens, Unit 1A Dryer Bypass Valve Opens, Unit 1A Instrument Air Low Pressure Alarms.

c. Unit 1A Dryer Bypass Valve Opens, 1A Service Air Backup Valve Opens, Unit 1A Instrument Air Low Pressure Alarms.

d. 1A Service Air Backup Valve Opens, Unit 1A Instrument Air Low Pressure Alarms, Unit 1A Dryer Bypass Valve Opens.

ANSWER d.

REFERENCE Lesson Plan 4701, Instrument Air NEW HIGHER Mark Jensen - Is this the sequence as it would happen in the plant? Sometimes the book setpoints do not match actual in-plant setpoints!

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SUBSORT

KA 295021A105

QUESTION The following plant conditions exist on Unit 1 prior to refueling:

- Unit 1 is in Mode 4 with A RHR operating in shutdown cooling.

- Reactor water temperature is 220 degrees F and steady.

- The B condensate booster pump is operating with RWCU rejecting to the condenser.

- Both Recirculation Pumps are OFF.

- Main Condenser backpressure is 26 inches Hg.

Control Room Operators then receive alarm 901-3 B-6, RHR PUMP TRIP.

- Reactor Dome Pressure is 35 psig and rising slowly.

- Reactor Metal Temperatures are rising slowly.

- Reactor Water level is being maintained between 25 inches and 35 inches.

To prevent thermal stratification from occurring, Operators should . . .

a. start a Reactor recirc pump.

b. raise Reactor Water level to >110 inches and perform a feed and bleed with RWCU.

c. raise Reactor Water level to between 90 inches and 100 inches and secure RWCU reject.

d. open a Main Turbine Bypass Valve and maintain Reactor Water level between 20 inches and 40 inches.

ANSWER a

REFERENCE QCOA 1000-02, Loss of Shutdown Cooling, Rev 14 QCAN 901-3 B-6, RHR Pump Trip, Rev 3 NEW HIGHER

QNUM 010

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KA 295023.A2.04

QUESTION Unit 2 is in a refueling outage. During core offload, the Fuel Handling Supervisor reported that a spent fuel assembly has been dropped in the spent fuel pool. Bubbles were seen rising from the damaged assembly. The immediate operator actions include which one of the following?

a. Evacuate all personnel from the refuel floor.

b. Evacuate all personnel from the refuel bridge only.

c. Verify proper operation of SBGTS PRIOR to evacuation of all personnel from refuel floor.

d. Direct the Fuel Handlers to retract refuel hoist PRIOR to evacuation of personnel from the refuel bridge.

ANSWER a.

REFERENCE QCFHP 0110-04, New/Irradiated Fuel Damage, Rev 3.

NEW FUNDAMENTAL

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QDATE 2007/06/04

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KA 295024 2.1.7

QUESTION A transient initiated on Unit 2. One minute later, the following was noted on the 902-3 panel:

- Drywell pressure is 4.5 psig and rising.

- Drywell air temperature is 240 degrees F and rising.

- Torus pressure is 3.0 psig and rising.

- Torus water temperature is 82 degrees F and rising.

Which of the following is indicated?

a. A safety valve opened but is now closed.

b. The Drywell to Torus d/p system is malfunctioning.

c. The containment is functioning normally after a LOCA.

d. A relief valve has failed open and its tail pipe is cracked in the torus air space.

ANSWER c.

REFERENCE LNF-1601, Primary and Secondary Containment, pgs 44 - 49.

295024 2.1.7 MODIFIED HIGHER

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KA 295025.K1.02

QUESTION A transient condition has occurred that has resulted in a high pressure condition in the Unit 1 reactor pressure vessel.

As pressure increases, which of the following would actuate FIRST to ensure vessel integrity?

a. RPS

b. Target Rock Valve

c. Low set Safety Valve

d. Electromatic Relief Valve

ANSWER a.

REFERENCE LF-0203, Safety & Relief Valve Configuration Horse Notes Dwg 0203-01, Rev 4 NEW FUNDAMENTAL

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KA 295026K305

QUESTION Unit 1 was at full power operation when Electromatic Relief Valve 1-203-3B spuriously opened.

With Torus water average temperature exceeding 110 degrees F, Operators placed RHR A in the Torus cooling mode. What additional action is required?

a. Blow down the reactor.

b. Depressurize the reactor to < 150 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. Lower Torus temperature to <95 degrees F within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. Place the Reactor Mode Switch in SHUTDOWN immediately.

ANSWER d.

REFERENCE QGA 200, Primary Containment Control, Rev 8 LNF-1601, Primary & Secondary Containment, pg 17 QCOP 100-09, Torus Cooling Startup and Operation, Rev 17 QCOA 1600-03, Torus Water High Temperature, Rev 11, pg 2, 3 NEW FUNDAMENTAL

QNUM 014

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KA 295028K204

QUESTION The following plant conditions exist on Unit 2:

- Unit 2 is in Mode 1, steady state.

- Drywell Average temperature is 135 degrees F and steady.

- Drywell pressure is 1.4 psig and steady.

- All other plant conditions are normal for full power operation.

Operators observed that temperatures in the vicinity of the inboard MSIV pilot solenoids have increased. No annunciator alarms have actuated.

With regard to the drywell cooling ventilation system, the most probable cause for this condition is . . .

a. the drywell coolers F and/or G are degraded.

b. the drywell cooler blowers have auto tripped.

c. there is a loss of RBCCW cooling to the drywell coolers.

d. a temperature control damper in the vicinity of MSIV pilot solenoids has failed closed.

ANSWER a.

REFERENCE LIC 1602, Containment Auxiliaries, pgs 45 - 49.

NEW HIGHER

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KA 295028K302

QUESTION Unit 2 has experienced a LOCA. With Drywell temperatures increasing, the Unit Supervisor ordered the U2 NSO to spray the Drywell before exceeding the Drywell Spray Initiation Limit.

The reason for initiating Drywell sprays is to . . .

a. prevent flashing of the RPV level instrument reference legs.

b. draw non-condensibles from the Torus back into the Drywell.

c. ensure the capabilities of the Drywell to Torus vacuum breakers are not exceeded.

d. ensure that a possible blowdown will not raise torus temperature or pressure above design limits.

ANSWER d.

REFERENCE QGA-200, Primary Containment Control Lesson Plan L-QGA-200a NEW FUNDAMENTAL

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KA 295030K302

QUESTION Which of the following systems operation is prohibited with a lowering Torus water level and why?

a. RCIC operation when Torus level drops below 10 feet because RCIC would lose NPSH.

b. HPCI operation when Torus level drops below 11 feet because the HPCI turbine exhaust would be exposed.

c. RCIC operation when Torus level drops below 12 feet because the RCIC turbine exhaust would be exposed.

d. HPCI operation when Torus level drops below 13 feet because HPCI would lose NPSH.

ANSWER b.

REFERENCE QC Bank question: 336293 QGA 200 states prevent HPCI ops less than 11 feet. QCOA 1600-05, Leak in Torus states scram at 12 feet. LN 2300 states the HPCI turbine steam exhaust enters the Torus water at a level of 11 feet. RCIC would expose exhaust NPSH too but is not a concern due to the volume of the exhaust. Loss of NPSH is not a concern due to suction from CCST or BOTTOM of Torus.

BANK HIGHER

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KA 295031A105

QUESTION A transient has occurred on Unit 1 with the following conditions existing:

- Reactor water level is -20 inches and lowering at 20 inches per minute.

- Reactor power is 7% and steady.

- HPCI, feedwater, and condensate systems are unavailable.

- QCOP 0250-02 has been completed, bypassing the Group I isolation.

- The MSIVs are OPEN.

- RPV pressure is being controlled using Turbine Bypass Valves.

The Unit Supervisor has ordered Reactor water level lowered to at least -35 inches. Regarding RCIC operation, operators will . . .

(1) (2)

a. TRIP RCIC. NO RPV injection is allowed.

b. TRIP RCIC. RCIC injection would cause a significant power excursion.

c. allow RCIC to inject. RCIC injection will be required for Reactor level control.

d. allow RCIC to inject. RCIC will be required for RPV pressure control.

ANSWER c.

REFERENCE QGA 100, RPV Control, Rev 8 QGA 101 RPV Control (ATWS), Rev 10 NEW HIGHER Will replace this question with one that Jensen has written.

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KA 295037A207

QUESTION Given the following plant conditions on Unit 2:

- APRMs read 10% and are steady.

- Reactor pressure is 970 psig and lowering.

- Drywell pressure is 1.7 psig and steady.

- Torus pressure is 0.2 psig and steady.

- The Reactor Mode switch is in SHUTDOWN.

- Reactor water level is -24 inches and lowering.

The SRO directing the QGAs ordered QCOP 0250-02, Bypassing MSIV Group I Isolation from Low Low Reactor Water Level be performed. Before any QCOP 0250-02 jumpers could be placed, a GROUP I isolation occurred due to Low Low reactor water level. The NSO assigned to perform QCOP 0250-02 continued with the procedure and completed placing the jumpers.

He is now ready to reset the Group I isolation, and the following plant conditions have changed:

- Reactor water level is -72 inches

- Reactor pressure is 1080 psig.

Assume there is no Group I high temperature or high steam line flow signal present. The NSO then places the MN STM ISOL RESET switch to the INBD and then OUTBD position. The GROUP I isolation . . .

a. will NOT reset, and the MSIVs and the steam line drain valves will REMAIN CLOSED.

b. resets, and the MSIVs and the steam line drain valves AUTOMATICALLY OPEN.

c. resets, and the MSIVs and the steam line drain valves REMAIN CLOSED.

d. resets, and the MSIVs remain closed but the steam line drain valves will AUTOMATICALLY OPEN.

ANSWER c.

REFERENCE LIC-0250, Main Steam lesson plan BANK (INPO bank Question 20823)

HIGHER

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KA 295038 2.3.11

QUESTION Running Turbine Building Ventilation . . .

a. ensures Turbine Building air is filtered prior to release to the environment.

b. ensures Turbine Building air is monitored prior to release to the environment.

c. ensures Turbine Building pressure is maintained lower than Reactor Building pressure.

d. allows an alternate lineup for the Standby Gas Treatment System to take a suction from the Turbine Building.

ANSWER b.

REFERENCE QGA-400, Radioactivity Release Lesson Plan, pg 5 295038 2.3.11 NEW FUNDAMENTAL

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KA 600000A105

QUESTION A fire has been reported behind the Main Turbine shield wall. Regarding ventilation, Control Room Operators MUST . . .

a. operate ventilation as directed by the Fire Pre-Plan book.

b. secure all Turbine Building Ventilation to prevent fanning the fire.

c. continue to operate Turbine Building Ventilation to remove smoke.

d. operate Turbine Building Ventilation as requested by the Fire Brigade Leader.

ANSWER d.

REFERENCE Fire Pre Plan Lesson Plan pgs 1 & 3.

NEW FUNDAMENTAL

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KA 295002K304

QUESTION The following plant conditions exist on Unit 1:

- Mode 1 at 30% reactor power and holding.

- Reactor pressure is being controlled by the Turbine Bypass Valves.

- Condenser backpressure is at 5 inches Hg and degrading rapidly.

As condenser vacuum is lost, the ___(1)____ will close on a ___(2)____ signal.

(1) (2)

a. Turbine stop valves (only) Loss of condenser vacuum

b. Turbine stop valves and turbine bypass valves Loss of condenser vacuum

c. Turbine stop valves and turbine bypass valves Reactor protection system

d. Main steam isolation valves Group I Isolation

ANSWER b.

REFERENCE Lesson Plan 0500, Reactor Protective System, pg 51 NEW HIGHER

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KA 295007A102

QUESTION Given the following conditions:

- Unit 1 was operating at full power, with no equipment out of service, when a Group 1 Isolation occurred due to a Main Feedwater line break.

- HPCI and RCIC are injecting.

- Reactor water level is -25 inches and rising.

- RPV Pressure is following the expected trend for automatic operation of ERVs.

Assuming the Operator has made no manipulations to HPCI:

HPCI pump flow is presently (higher than / the same as) , and HPCI pump speed is (higher than / the same as) as it would be if the Main Steam lines were NOT isolated and RPV pressure was being controlled by the Main Turbine Bypass Valves.

Flow Speed

a. higher than higher than

b. higher than the same as

c. the same as higher than

d. the same as the same as

ANSWER c.

REFERENCE LN-2300 High Pressure Coolant Injection LIC-0203 Automatic Depressurization System NEW HIGHER

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QDATE 2007/06/04

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KA 295008A205

QUESTION Unit 2 was operating at 75% reactor power when it scrammed due to a loss of EHC. After the scram recovery, reactor water level increased to +35 inches and then began LOWERING with a feedwater flow indication of ZERO.

Moments later, ALL Reactor Feed Pumps TRIPPED due to a faulty low suction pressure switch.

At -30 inches reactor water level, the NSO restarted the A RFP and manually OPENED a FWRV. At +42 inches Reactor water level, the NSO CLOSED all Main FWRVs. Several minutes later, all Main FRVs were manually CLOSED by their controller. Two minutes later the NSO noted that RPV water level was +49 inches and the A RFP was TRIPPED.

What caused RPV level to reach this level?

a. Condensate/booster pumps are injecting.

b. Decay heat is affecting the water injected.

c. HIGH pressure ECCS pumps are injecting.

d. The FWLC system is holding open a FWRV.

ANSWER b.

REFERENCE Explanation: Relatively cool feed water will swell when it is heated.

QC Bank Question 351373 MODIFIED HIGHER

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KA 295009K301

QUESTION Unit 2 was operating at 95% of rated power when the oil system pressure on the C reactor feedwater pump lowered to 4 psig. What effect does this condition have on the recirculation system without operator action?

a. The Recirc Pumps will immediately run back to 70%.

b. The Recirc Pumps will immediately run back to minimum.

c. When Reactor water level reaches 26 inches within 45 seconds, the Recirc Pumps will run back to minimum.

d. When Reactor water level reaches 26 inches within 45 seconds, the Recirc Pumps will run back to 70%.

ANSWER d.

REFERENCE QC Bank question: 295449 LF-0202, Recirculation System Lesson Plan MODIFIED HIGHER

QNUM 025

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KA 295009 2.1.31

QUESTION Unit 1 was operating at 85% power with the feedwater level control (FWLC) system in AUTO, and in 3-Element control.

The NSO received a reactor scram signal and noted that Reactor Water Level lowered to +5 inches before recovering. About 15 seconds after the scram, the NSO observed that Reactor Water Level was responding sluggishly to the level demand.

The NSO determined that the FWLC system _____(1)_____ and responds by ____(2)_____ .

(1) (2)

a. was NOT operating properly taking FWLC to MANUAL

b. was NOT operating properly taking FWLC to single-element

c. WAS operating properly verifying feedwater flow is 15% for <2 minutes after the scram

d. WAS operating properly verifying reactor water level returns to >15 inches within >2 minutes after the scram

ANSWER c.

REFERENCE Lesson Plan 0600, Feedwater, pgs 31 -33.

NEW HIGHER

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KA 295036A104

QUESTION Unit 2 is operating in Mode 1. A Non-Licensed Operator reported to the Control Room that the Unit 2 Torus room water level was about 3 inches with the room sump pump operating. To prevent an uncontrolled release of radioactivity to the environment, the water will be filtered by the Radioactive Liquid Waste system by first being pumped to the ____________ .

a. Waste Collector Tank

b. Floor Drain Surge Tank

c. Floor Drain Collector Tank

d. Floor Drain Sample Tank

ANSWER c.

REFERENCE Lesson Plan 2000, Radioactive Liquid Waste System, pgs 8 & 9.

P&ID 2000, Radioactive Liquid Waste System.

NEW FUNDAMENTAL

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KA 500000K208

QUESTION A severe accident has occurred on Unit 2 that has resulted in fuel damage and hydrogen release. The following atmospheric conditions exist in Unit 2 primary containment:

- Drywell Hydrogen 5%

- Torus Hydrogen 5%

- Drywell Oxygen 3%

- Torus Oxygen 3%

- Drywell pressure 4 psig

- Torus pressure 3 psig QGA 200-5, Hydrogen Control, has the Operators vent the Torus and Drywell for hydrogen control. Assuming that the offsite release rate is expected to stay below the LCO during venting, which vent path is an NSO required to use first?

a. Vent the Torus using the Hardened Vent.

b. Vent the Drywell using the Drywell/Torus purge fans.

c. Vent the Torus through the Standby Gas Treatment system.

d. Vent the Drywell through the Standby Gas Treatment system.

ANSWER c.

REFERENCE QGA 200-5, Hydrogen Control, Rev. 5 QCOP 1600-13, Post Accident Venting of Primary Containment, Rev. 19 NEW HIGHER

QNUM 028

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 203000A109

QUESTION Torus Spray was being tested on Unit 1 when a Recirc System leak resulted in a reactor scram and entry into the QGAs on high Drywell pressure and low RPV level. The NSO established Torus Spray, and Torus Cooling. The MO 1-1001-16A, RHR HX Bypass Valve, is fully closed.

The NSO notes that the maximum RHRSW flow with the MO 1-1001-5A, RHR HX SW Disch Valve, full open is 2500 gpm at a discharge pressure of 275 psig.

Which action(s) (if any) should be taken to correct the RHRSW System operation?

a. Start a 2nd RHRSW Pump.

b. Cross-tie the A and B RHRSW loops.

c. None, adequate RHRSW flow has been achieved.

d. Stop the RHRSW Pump, reverse heat exchanger flow and restart the RHRSW Pump.

ANSWER d.

REFERENCE QC Bank question 295445 QCOP 1000-04, RHR Service Water System Operation, Rev. 18 LNF-1000, RHR System Lesson Plan BANK HIGHER

QNUM 029

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 203000A203

QUESTION A LOCA is in progress on Unit 1. RHR Loop Select Logic has determined that there is NO difference between A and B Jet Pump Riser pressures. MO 1-1001-29B fails to automatically open when the reactor low pressure permissive is satisfied. RPV level is -85 inches.

Regarding LPCI injection into the RPV; the Operator _____(1)_____ , and the injection valves

____(2)_____ .

a. (1) is directed to reset the LPCI Loop Select Logic (2) will open automatically

b. (1) is directed to reset the LPCI Loop Select Logic (2) can then be manually opened using the control switches on 901-3 panel

c. (1) can NOT maintain the injection valves open from the Control Room (2) must be manually opened locally

d. (1) can NOT maintain the injection valves open from the Control Room (2) must be remotely opened from the valve motor breakers

ANSWER c.

REFERENCE QC Bank Question 109010 MODIFIED HIGHER

QNUM 030

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 205000A202

QUESTION The following plant conditions exist on Unit 1 prior to refueling:

- Unit 1 is in Mode 4 with A RHR operating in shutdown cooling.

- Reactor Pressure is 95 psig and rising slowly.

- Reactor Temperature is 220 degrees F and steady.

- Reactor Water level is being maintained between +20 inches and +40 inches.

- The B condensate booster pump is operating with RWCU rejecting to the condenser.

- Reactor Recirculation Pumps are off.

Control Room Operators then receive the following alarm:

- Alarm 901-3 B-6, RHR PUMP TRIP This condition was caused by _____(1)_____ and Operators should _____(2)_____.

a. (1) MO 1-1001-43 closing on increasing reactor pressure; (2) lower reactor pressure by increasing RWCU reject

b. (1) MOs 1-1001-47 and 1-1001-50 closing on increasing reactor pressure; (2) lower reactor pressure by increasing RWCU reject

c. (1) A Group II isolation occurring on low reactor water level; (2) increase reactor water level by opening the feedwater regulating valve

d. (1) shutdown cooling low pressure permissive tripping RHR pump on high reactor pressure; (2) reset the low pressure condition by depressing the isolation valves reset switch on the 901-3 panel.

ANSWER b.

REFERENCE QCOA 1000-02, Loss of Shutdown Cooling, Rev 14 QCAN 901-3 B-6, RHR Pump Trip, Rev 3 NEW HIGHER

QNUM 031

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 205000A303

QUESTION Unit 1 is shutdown with refueling operations in progress. 1C RHR pump is in shutdown cooling operation at 3500 gpm. Maintenance personnel are locally cycling MO 1-1001-37B for testing.

If refueling water was draining into the Torus during valve testing, Operators would detect valve

_____(1)_____ open indication and ______(2)_______ .

(1) (2)

a. MO 1-1001-34B; FR 1-1040-7, RHR FLOW lowering

b. MO 1-1001-36B; FI 1-1040-11B, CTMT SPRAY FLOW rising

c. MO 1-1001-36B; PI 1-1040-2B, RHR HX INLET pressure lowering.

d. MO 1-1001-34B; Annunciator Alarm 901-3 A-5 CNMT SPRAY A or B LOW FLOW Alarm NOT reset

ANSWER d.

REFERENCE RHR Lesson Plans LNF-1000 QCAN 901-3 A-5, RHR Pump Running and Low Flow to Containment Spray Header, Rev 1 NEW HIGHER

QNUM 032

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 206000A304

QUESTION Unit 2 HPCI is operating during an accident with the following plant conditions:

- Reactor pressure 100 psig, lowering.

- Drywell pressure 2.0 psig, steady.

The plant responds by closing the following valves, associated with the AC trip logic . . .

a. MO 2-2399-4, Inbd Steam Isolation valve ONLY.

b. MO 2-2301-5, Outbd Steam Isolation valve ONLY.

c. MO 2-2301-40, Vacuum Breaker Isolation valve AND MO 2-2301-5, Outbd Steam Isolation valve.

d. MO 2-2399-40, Vacuum Breaker Isolation valve AND MO 2-2301-4, Inbd Steam Isolation valve.

ANSWER a.

REFERENCE QCAN 901-3 D-9, HPCI GROUP 4 PRIMARY CONTAINMENT ISOL VLVS AC TRIP CHANNEL DIVISION ISOLATION, Rev 10 QCAN 901-3 D-10, HPCI GROUP 4 PRIMARY CONTAINMENT ISOL VLVS DC TRIP CHANNEL DIVISION ISOLATION, Rev 10 NEW HIGHER

QNUM 033

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 206000A410

QUESTION Maintenance personnel in the HPCI room are monitoring the HPCI booster pump using a tachometer and want Control Room Operators to adjust the HPCI turbine speed to obtain a booster pump speed of 1500 rpm.

What would Control Room Operators set the HPCI turbine speed at to obtain this reading?

a. 750 rpm

b. 1500 rpm

c. 3000 rpm

d. 4500 rpm

ANSWER c.

REFERENCE HPCI Lesson Plan 2300, pg 9 NEW HIGHER

QNUM 034

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 209001A403

QUESTION A transient has occurred on Unit 1 with the following conditions existing:

- Reactor pressure is 275 psig.

- Reactor water level is -68 inches.

- The A Core Spray line break detection d/p is 1.2 psid.

- MO 1-1402-24A has dual position indication.

- MO 1-1402-25A has a CLOSED position indication.

- The A Core Spray pump is RUNNING.

Discharge valve MO 1-1402-25A indicates closed because . . .

a. it must wait for the 8.5 minute timer to time out.

b. the Core Spray injection valve logic has failed.

c. MO 1-1402-24A must reach FULL OPEN before MO 1-1402-25A opens.

d. the Core Spray line break detection system has inhibited MO 1-1402-25A from opening.

ANSWER b.

REFERENCE Core Spray Lesson plan LIC-1400, pgs 4, 8, 15 NEW HIGHER

QNUM 035

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 600001A216

QUESTION There is a severe, uncontrolled fire on Unit 2. It is in an area where Unit 2 RCIC cables are routed.

Which of the following systems is the preferred RPV injection source which will meet the requirements of Appendix R?

a. U2 Condensate/Feedwater

b. Safe Shutdown Makeup Pump

c. U1 Reactor Core Isolation Cooling Pump

d. U2 High Pressure Coolant Injection Pump

ANSWER b.

REFERENCE QCARP 0030-02, TB-I Injection with SSMP and Bringing the Unit to Cold Shutdown, Rev 8 Lesson Plan 2900, Safe Shutdown Makeup Pump Learning Objective N-2900-K01, SR-2900-K01 K/A selected to track selection of shutdown makeup pump, not fire.

NEW FUNDAMENTAL

QNUM 036

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 211000K102

QUESTION Core plate differential pressure low pressure is sensed from the ____(1)_____ and the core plate differential pressure high pressure is sensed from the _____(2)______.

(1) (2)

a. standby liquid control outer pipe standby liquid control injection pipe

b. standby liquid control injection pipe standby liquid control outer pipe

c. calibrated jet pump #11 RPV bottom head drain

d. loop B core spray sparger RPV bottom head drain

ANSWER a.

REFERENCE SBLC Lesson Plan 1100 Recirculation system ppt presentation pg 45, Core DP and SLC nozzle Reactor Vessel and Internals Lesson Plan 0201 NEW HIGHER

QNUM 037

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 212000K201

QUESTION Bus 29-2 has tripped. How does this affect the U2 Reactor Protection System (RPS)?

a. RPS MG set A trips 1/2 scram occurs.

b. RPS MG set A trips NO effect on RPS.

c. RPS MG set B trips NO effect on RPS.

d. RPS MG set B trips 1/2 scram occurs.

ANSWER d.

REFERENCE Lesson Plan 500, RPS, pgs 3, 37.

QCAN 901-5 A-10, RPS Channel A Reactor Scram NEW HIGHER

QNUM 038

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 215003K304

QUESTION Unit 2 is in startup mode. Following a Control Rod withdraw, the NSO received the following TWO alarms:

- 902-5 A-5, IRM HIGH

- 902-5 C-3, ROD OUT BLOCK This condition was caused by . . .

a. improper detector ranging.

b. loss of IRM detector high voltage.

c. an IRM drawer module that was unplugged.

d. an IRM function switch that was out of the OPERATE position on an IRM drawer.

ANSWER a.

REFERENCE QCAN 902-5 A-5, IRM HIGH, Rev 6 QCAN 902-5 C-10, Channel A IRM HIGH HIGH or INOP, Rev 6 NEW FUNDAMENTAL

QNUM 039

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 215004K405

QUESTION An upward spike has occurred on Unit 1 SRM 23. Neutron level then returned to normal. How will the resulting UPSCALE HIGH alarm clear on the 901-5 panel?

a. It will automatically clear since the condition has cleared.

b. The Operator must momentarily take the SRM Bypass switch to 23' position.

c. The NSO must place the RESET switch on SRM 23 drawer to the TRIP position

d. The NSO must take the RESET switch on SRM 23 drawer to the TRIP position AND momentarily take the SRM Bypass switch to the 23' position.

ANSWER a.

REFERENCE Lesson Plan 701, SRMs, pg 11, 20 QCAN 901-5 A-4, SRM Channel high or Inop, Rev 5 NEW FUNDAMENTAL

QNUM 040

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 215005K505

QUESTION With Unit 2 in Mode 1 on the 60% rod line, NSOs raise recirculation flow with both pumps to 80% of rated drive flow. This would raise the APRM Flow Biased scram set point to . . .

a. 108%.

b. 112%.

c. 116%.

d. 125%.

ANSWER b.

REFERENCE Lesson Plan 703, APRM QCOP 0700-04, APRM System Operation, Rev 15 APRM Scram in Run Mode (2 loop operation) = (.56 Wd + 67.4%)

NEW HIGHER

QNUM 041

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 217000K601

QUESTION While operating Unit 1 RCIC for a surveillance test, the NLO in the RCIC room reported that the RCIC vacuum pump and condensate pump failed to start. This failure most likely was due to loss of power from . . .

a. 125 Volts DC Bus 1A.

b. 125 Volts DC Bus 2A.

c. 250 Volts DC MCC 1B.

d. 250 Volts DC MCC 1A.

ANSWER c.

REFERENCE RCIC Lesson Plan 1300, pg 41 of 62 NEW FUNDAMENTAL

QNUM 042

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 218000A101

QUESTION Unit 2 is at 100% power. No testing is in progress. The ANSO reports that ADS valve 2-202-3B has a tailpipe temperature of 210 degrees F and stable. This indicates that . . .

a. the valve is lifting.

b. the tailpipe is at ambient conditions, the valve has NOT lifted.

c. the valve has seat leakage, but there are no immediate concern of valve operability.

d. the valve has a significant seat leak and valve operability must be evaluated immediately.

ANSWER c.

REFERENCE Lesson Plan 0203 ADS, pgs 12 & 28 QCOS 0203-03, Main Steam Relief Valves Operability Test, Rev 23 NEW FUNDAMENTAL

QNUM 043

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 223002A204

QUESTION You are the Unit 1 NSO. After a change in reactor power on Unit 1, you observe the following conditions:

Annunciator 901-5 B-9, Channel A MSL Hi-Hi Radiation Alarm In alarm Annunciator 901-5 B-16, Channel B MSL Hi-Hi Radiation Alarm NOT alarming Annunciator 901-3 A-2, MSL High Radiation NOT alarming Based on the above, you. . .

a. manually INITIATE a Group II isolation AND a Reactor scram.

b. VERIFY automatic actions have occurred and you must scram the reactor.

c. do NOT initiate any isolations, and you must MONITOR all main steam line radiation monitors.

d. do NOT initiate any isolations, and you must LOWER reactor power until alarm condition clears.

ANSWER c.

REFERENCE QCAN 901-5 B-9, Channel MSL Hi-Hi Radiation, Rev 8 QCAN 901-3 A-2, MSL Hi Radiation, Rev 10 QCOA 1700-05, Abnormal Main Steam Line Radiation, Rev 13 NEW HIGHER

QNUM 044

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 239002A301

QUESTION To prevent reopening of an ADS relief valve, within _____(1)_______ seconds of valve closure, the interlock timers have been set for approximately _____(2)_______ seconds.

(1) (2)

a. 4 14

b. 10 14

c. 14 20

d. 20 24

ANSWER b.

REFERENCE QCOP 0203-01, Reactor Pressure Control Using Manual Relief Valve Actuation, Rev 12 Lesson Plan 0203, ADS NEW FUNDAMENTAL

QNUM 045

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 259002A404

QUESTION With Unit 2 operating at 100% power, the Control Room Operators receive the following alarms:

- 902-5 C-8, 2A FW ACTUATOR TROUBLE

- 902-5 H-8, 2B FW ACTUATOR TROUBLE A Non-Licensed Operator set to investigate the annunciators reported back that there must have been a momentary loss of the control signal, but that everything at the local skid looks normal EXCEPT that neither FWRV appears to be moving like the NLO is used to seeing on rounds.

This condition _____________ after Control Room Operators null the deviation between FWRV demand and indicated position.

a. will automatically reset immediately

b. will automatically reset after a time delay

c. must be manually reset from the Control Room

d. must be manually reset locally at the FWRV hydraulic control station

ANSWER c.

REFERENCE Lesson Plan 600, Digital RPV Level Control QCOP 0600-21, Operation of Feedwater Level Control System, Rev 12 NEW FUNDAMENTAL

QNUM 046

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 261000 2.1.27

QUESTION The charcoal filter in the Standby Gas Treatment System (SBGTS) is designed primarily to remove . . .

a. at least 99% of radioactive particles >0.3 microns in size.

b. radioactive isotopes of iodine released during an accident.

c. inert and halogenated fission products released to the primary containment.

d. dust particles and other debris that have been entrained into the system flow.

ANSWER b.

REFERENCE Lesson Plan 7500, SBGTS.

261000 2.1.27 NEW FUNDAMENTAL

QNUM 047

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 262001K103

QUESTION Unit 2 is operating at full power with a normal electrical lineup, EXCEPT that 345KV GCB 8-9 is OPEN for maintenance activities.

An electrical fault has deenergized Line 0402, the 345 KV line to Cordova, that results in a trip of the Unit 2 turbine generator. After the electrical transient has stabilized, and with no Operator action, Bus 23 is ____(1)_____ and Bus 24 is ____(2)____ .

(1) (2)

a. powered from T21 powered from T21

b. de-energized de-energized

c. powered from T22 powered from T22

d. de-energized powered from T22

ANSWER b.

REFERENCE Lesson Plan 6500, 4KV Distribution 345 KV Switchyard Drawing 6100-01, Rev 3.

NEW HIGHER

QNUM 048

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 262002K301

QUESTION With Unit 1 operating at 100% power, a loss of ESS power occurred. Regarding the feedwater level control circuitry, this condition would immediately result in a . . .

a. silent lockup of the 1A FWRV.

b. Nematron system alarm.

c. BLAC system alarm.

d. Feedwater Regulator Hydraulic Power Unit Trouble alarm.

ANSWER a.

REFERENCE Lesson Plan 0600 Feedwater Level Control System, Pg 83, 84 NEW FUNDAMENTAL

QNUM 049

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 263000.K2.01

QUESTION A maintenance worker reports to the control room that he accidently de-energized 250 VDC Turbine Building MCC 2. What Reactor Building (RB) busses would be affected by this action?

a. RB MCC 2A Main Feed AND RB MCC 2B Reserve Feeds ONLY

b. RB MCC 2A Main Feed AND RB MCC 2B Reserve Feeds AND RB MCC 1B Main Feed

c. RB MCC 2 Main Feed AND RB MCC 1A Main Feed AND RB MCC 1B Reserve Feed

d. RB MCC 2A Reserve Feed AND RB MCC 2B Main Feed ONLY

ANSWER b.

REFERENCE QOM 2-6900-10, Rev 4.

QOM 1-6900-10, Rev 5 NEW FUNDAMENTAL

QNUM 050

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 264000K407

QUESTION When locally starting the Emergency Diesel Generator, the maintenance toggle switch on the Engine Mounted Control Panel must be in the REMOTE AUTOSTART position, otherwise . . .

a. the EDG Cooling Water Pump will not auto start.

b. the generator field will NOT flash when the EDG is started.

c. the normal engine trips will NOT be available during manual operation.

d. the undervoltage load shedding of nonessential loads will NOT occur automatically following a LOOP.

ANSWER b.

REFERENCE QCOP 6600-11, Diesel Generator Local Operation, Rev. 21 Lesson Plan 6600, EDG, pg 57 NEW FUNDAMENTAL

QNUM 051

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 300000K513

QUESTION An NLO on rounds identified the following conditions associated with the 1A Instrument Air compressor air dryer:

- Instrument air header pressure is 95 psig and steady.

- Dryer Pre-filter d/p is 2 psid and steady.

- Dryer After-filter d/p is 10 psid and slowly rising.

- The CHAMBER PERFORMANCE DEGRADING alarm is Clear.

These conditions are . . .

a. normal.

b. caused by a loss of pilot air.

c. caused by desiccant break through.

d. caused by moisture overload in the system.

ANSWER c.

REFERENCE Lesson Plan 4701 Instrument Air, pgs 24 - 27, 60 NEW HIGHER

QNUM 052

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 400000K601

QUESTION Unit 2 was at 100% power in January, when maintenance personnel inadvertently cut into the Instrument Air line supplying the Unit 2 Reactor Building.

As the Instrument Air system slowly depressurizes, what affect would this have on the RBCCW system or systems cooled by the RBCCW system?

a. An increase in drywell pressure.

b. Degraded lubrication of the Reactor Recirc pump motor bearings.

c. The ability to manually and automatically replenish the RBCCW expansion tank is lost.

d. High temperature in the RWCU non-regenerative heat exchanger return to the recirculation system.

ANSWER b.

REFERENCE QCOP 0202-29, Unit Reactor Recirculation Oil System Start-up and Operation, Rev 4 Lesson Plan 3700, RBCCW, pg 30 Lesson Plan 1200, RWCU , pg 51 NEW HIGHER

QNUM 053

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 263000A101

QUESTION Unit 1 was operating at full power when a loss of offsite power occurred.

- HPCI was trip-latched when DW pressure was 1.7 psig and RISING.

- Reactor water level lowered to +20 inches when RCIC was manually started for injection.

Presently:

- Reactor Water Level is +25" and STEADY.

- DW pressure is 4 psig and STEADY.

Which one of the loads listed below will have the greatest impact on the discharge rate of the Unit 1 Safety Related 250VDC battery?

a. HPCI Auxiliary Oil pump.

b. HPCI Emergency Oil pump

c. Main Turbine Emergency Bearing Oil pump.

d. RCIC Barometric Condenser Condensate pump.

ANSWER a.

REFERENCE QC Bank Question 351400 BANK HIGHER Explanation: At 2.5 psig in the DW, HPCI will receive an autostart signal causing the the HPCI aux oil pump to start. It is a large load off the DIV I (Unit 1) essential battery. The HPCI EBOP is a large load on the battery but will not be running. If HPCI had been allowed to autostart before it was trip-latched the EBOP would be running. The main turbine EBOP will be running but is a load on the NON-essential 250VDC battery. The RCIC barometric condenser condensate pump will be running but is a load on the DIV II (Unit 2) battery. Technical

Reference:

QOM 1-6300-T08, QCOA 2300-01

QNUM 054

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 202001K410

QUESTION Unit 2 experienced a Recirculation Pump trip from 100% power due to the pump discharge valve going to the fully closed position. Preparations are being made to restart the pump.

The recirculation pump can be restarted following the trip, since the discharge valve closure pump trip is . . .

a. removed from the start circuitry after the discharge valve is full closed.

b. removed from the start circuitry as soon as the pump speed is indicating 0% after the trip.

c. bypassed by setting the pump speed demand signal to 14% during preparation for pump start.

d. removed from the start circuitry as soon as the motor-generator set breaker is tripped and the pump is coasting down.

ANSWER a.

REFERENCE QC Bank question 106169 Justification: Discharge Valve interlock start RE3 BANK FUNDAMENTAL

QNUM 055

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 202002K604

QUESTION Unit 1 was operating at 95% of rated power when Control Room Operators received the following alarms:

- 901-6 F-5, CONDENSATE BOOSTER PUMP AUTO TRIP

- 901-4 F-7, RECIRCULATION LOOP FLOWS LIMITED BY FEEDWATER FLOW AND REACTOR VESSEL LEVEL The Operators observe that:

- The C Condensate/Condensate booster pump indicates tripped.

- Reactor Feedwater Pump suction pressure stabilized at about 155 psig.

- Recirc flow controllers transferred to Manual.

Operators regain control of Reactor water level at +15 inches and rising.

NO additional automatic actions occur. The Operators respond by . . .

a. inserting a reactor scram.

b. attempting to restart the C booster pump.

c. returning Recirc flow controllers to Auto.

d. lowering Reactor Recirc pump speed to 70%.

ANSWER d.

REFERENCE QCAN 901-4, F-7, Recirc Loop Flows Limited by Feedwater Flow and RPV level, Rev 4 QCAN 901-5, F-8, RPV Low Level, Rev 10 QCAN 901-6 F-5, Condensate Booster Pump Auto Trip, Rev 6 QCOA 3300-01, Loss of Condensate Pump, Rev 17 NEW HIGHER

QNUM 056

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 204000K504

QUESTION Unit 1 is at 97% power when a valving error in the RWCU room results in the A train of non-regenerative heat exchangers becoming isolated. The following annunciator alarms (assume that this is the ONLY alarm received):

- 901-4 F-12, CU SYSTEM AFTER NON-REGEN HX HIGH TEMP The operators actions are to . . .

a. lower RBCCW system temperatures.

b. VERIFY a Group III isolation has occurred.

c. immediately trip the operating RWCU pump(s).

d. isolate RWCU system before non-regenerative heat exchanger outlet temperature reaches 140 degrees F.

ANSWER d.

REFERENCE QCAN 901-4 F-12, RWCU Non-Regenerative Heat Exchanger Outlet High Temperature, Rev 7 NEW FUNDAMENTAL

QNUM 057

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 214000A201

QUESTION Unit 1 is in startup mode. Operators were withdrawing in-sequence control rod K14 from notch 24 to notch 36. Under these circumstances, the reed switch associated with rod K14 did not actuate for position 32. The plant response is ____(1)______ and the Operator actions would be to ___(2)____.

(1) (2)

a. a rod withdraw block would occur verify rod motion stopped

b. annunciator RPIS INOP would alarm stop rod motion

c. the Rod Worth Minimizer would alarm stop rod motion

d. no alarm would occur continue rod motion until the rod reaches position 36

ANSWER b.

REFERENCE QCAN 901-5 G-5, RPIS INOP Alarm, Rev 5 QCOA 0280-01, RPIS Failure, Rev 10.

NEW HIGHER

QNUM 058

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 215001A103

QUESTION Unit 1 is at 96% power with the Traverse In-Core Probe System (TIPS) operating for a surveillance. Upon a valid Group II actuation, the isolation of TIPS occurs by . . .

a. manually firing the shear valve.

b. automatic retraction of the cable, then manual closing of the ball valve as soon as the detector clears the indexer.

c. automatic retraction of the cable, then automatic closing of the ball valve after the detector enters the shield chamber.

d. manual retraction of the cable, then automatic firing of the shear valve.

ANSWER c.

REFERENCE Lesson Plan 0704, TIPS, pgs 6, 7, 14, 24 Lesson Plan 1603, Primary Containment Isolation, pg 12.

NEW FUNDAMENTAL

QNUM 059

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 215002A302

QUESTION Unit 1 is operating at 45% reactor power. No LPRMs or APRMs are bypassed. The NSO selects in-sequence rod R-9 for rod withdraw and notices that the Rod Block Monitor (RBM) recorder on the 901-5 panel goes downscale. This indication is due to . . .

a. an edge rod being selected.

b. insufficient LPRM inputs to the RBM.

c. insufficient neutron flux in the vicinity of rod R-9.

d. the RBM is automatically bypassed at this power level.

ANSWER a.

REFERENCE Lesson plan 0705 Rod Block Monitor, pgs 4, 9-11.

Horse Notes Dwg 0280-05, Rod Select Matrix NEW HIGHER

QNUM 060

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 216000A401

QUESTION The RPV Metal Temperature recorder 1-0263-104 can be found in the ___(1)____ and it senses and records the ____(2)_____ metal temperatures.

(1) (2)

a. Aux Electric Room Vessel Head Flange and FW Nozzle

b. Aux Electric Room Vessel Bottom Head and Steam Outlet Nozzle

c. Control Room Vessel Head Flange and FW Nozzle

d. Control Room Vessel Bottom Head and Steam Outlet Nozzle

ANSWER c.

REFERENCE QC Bank Question 105362 ILT.04177: RPV temp recorder location and sensing points.

MODIFIED HIGHER

QNUM 061

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 219000 2.4.18

QUESTION An accident has occurred on Unit 2. The Unit Supervisor entered QGA 200, Primary Containment Control. The operating crew could NOT control Torus water temperature and entered QGA 500-1, RPV Blowdown due to exceeding . . .

a. Heat Capacity Limit.

b. Primary Containment Pressure Limit.

c. Pressure Suppression Pressure.

d. Drywell Spray Initiation Limit.

ANSWER a.

REFERENCE QGA 200, Primary Containment Control, Rev 8 219000 2.4.18 NEW FUNDAMENTAL

QNUM 062

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 223001K101

QUESTION Unit 1 is in Mode 3, cooling down for a refuel outage. De-inerting is in progress using Reactor Building Vents. Reactor vessel water level drops to -2 inches due to a valving error and then recovers to normal level. Which of the following is NOT true. The _____(1)_____, if running, will trip due to a _____(2)_______.

(1) (2)

a. pumpback air compressor low suction pressure

b. drywell/torus purge fan Group II signal

c. the CAM sample pump and bypass pump low suction pressure

d. reactor building floor drain sump pump Group II signal

ANSWER c.

REFERENCE QC Bank question 100631 All of the distractors will be affected by a group II isolation at +0 inches with the exception of the CAM system which is a post-accident monitoring system and has its own suction valves that do NOT close on a group II signal!

Lesson Plan 1602, pgs 28, 43, 66, 90 MODIFIED HIGHER

QNUM 063

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 226001K202

QUESTION Unit 2 is in Mode 1. A LOOP/LOCA occurs. Relief valves are cycling to control reactor pressure. The following annunciators are in alarm:

- Annun 902-8, C-7, DIESEL GENERATOR 1 FAILED TO START

- Annun 902-3, E-7, RHR SYSTEM BUS 13-1 SUPPLY FROM 1/2 EDG Non-Licensed Operators have been dispatched to the affected diesel generators.

Under these conditions, which of the following should be used, if the Unit Supervisor directs you to establish Torus cooling?

a. A and B RHR pumps

b. C and D RHR pumps

c. A and C RHR pumps

d. B and D RHR pumps

ANSWER a.

REFERENCE QOM 2-6500-T05, Bus 23-1, 4160V AC, Rev 8 QOM 2-6500-T06, Bus 24-1, 4160V AC, Rev 7 Annun 902-8, C-7, Diesel Generator 2 Failed to Start Annunciator, Rev 3 Annun 902-3, E-7, RHR System Bus 13-1 Supply from 1/2 EDG , Rev 4 NEW HIGHER

QNUM 064

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 241000K302

QUESTION Unit 2 was operating at 97% power with the A EHC pressure regulator controlling reactor pressure at 1002 psig. The A EHC pressure regulator then failed downscale.

With NO Operator action, the backup pressure regulator will control reactor pressure at . . .

a. 996 psig.

b. 999 psig.

c. 1002 psig.

d. 1005 psig.

ANSWER d.

REFERENCE Lesson Plan 5652, pg 38 NEW FUNDAMENTAL

QNUM 065

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 233000K406

QUESTION Both Units are in Mode 1. The U1 and U2 spent fuel pools are connected through the transfer canal. Maintenance activities in the U1 spent fuel pool have just started, and resulted in a release of styrofoam blocks on the surface of the pool. The styrofoam has clogged the weir plates on the SOUTH side of the Unit 1 spent fuel pool.

Without Operator actions, the spent fuel pool water level will ___________.

a. lower, resulting in a trip of the operating SFP pump

b. rise, resulting in SFP water overflowing into the pool ventilation ducts

c. rise slightly as the pool overflow will be controlled by the remaining weir plates

d. vary due to intermittent draining/refilling of the skimmer surge tank and the automatic tripping/restarting of the spent fuel pool pump

ANSWER c.

REFERENCE Lesson Plan 1900, Spent Fuel Pool system, pgs 5, 8, 9 Figure 1900-01, Refuel Floor Layout, Horse Notes.

NEW HIGHER

QNUM 066

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.1.3

QUESTION In accordance with the Shift Turnover Procedure, choose the list below that includes activities (but not all activities) that are included on the shift turnover sheets.

a. LCO status, completed C/O checklists, panel annunciators in alarm.

b. Completed C/O checklists, panel annunciators in alarm, electric operation/transmission system changes.

c. LCO status, panel annunciators in alarm, electric operation/transmission system changes.

d. LCO status, completed C/O checklists, electric operation/transmission system changes.

ANSWER c.

REFERENCE OP-AA-20, Rev 0, Conduct of Operations Process Description OP-AA-112-101, Rev 2, Shift Turnover NEW FUNDAMENTAL

QNUM 067

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.1.18

QUESTION In accordance with OP-AA-111-101, Operating Narrative Logs and Records, the Unit Control Room log . . .

a. is maintained by the Unit Supervisor.

b. may be created or printed with blue ink.

c. must be devoid of any wit, irony and sarcasm.

d. must be complete, legible, accurate, and understandable.

ANSWER d.

REFERENCE OP-AA-111-101, Operating Narrative Logs and Records, Rev 5 NEW FUNDAMENTAL

QNUM 068

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.1.23

QUESTION Unit 1 was operating at 100% power with the main generator regulator being operated in manual. Non-Licensed Operators notified the Control Room that all Unit 1 Generator Hydrogen Seal Oil pumps have tripped. Hydrogen pressure dropped and finally stabilized at 40 psig.

Given the resulting hydrogen pressure for this condition and the attached generator capabilities curve, which of the following represents an allowed station output with the HIGHEST power factor?

a. 800 Mw 250 MVARs

b. 800 Mw 150 MVARs

c. 700 Mw 250MVARs

d. 600 Mw 300MVARs

ANSWER b.

REFERENCE QCOP 6000-2, Adjusting VARS on the Main Generator, Rev 7 QCGP 3-1, Attachment A, Reactor Power Operations, Rev 51 MODIFIED HIGHER

QNUM 069

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.2.24

QUESTION The following Unit 2 plant conditions are given:

- Reactor power is 40%.

- QCOS 1300-5, "Quarterly RCIC Pump Operability Test" is in progress.

- Torus water temperature is 77 degrees F and increasing at 3 degrees F every 15 minutes.

- Torus cooling is in operation.

What is the MAXIMUM amount of time this test may continue without Tech Specs requiring the test to be terminated?

a. 90 minutes

b. 140 minutes

c. 165 minutes

d. 215 minutes

ANSWER b.

REFERENCE TS 3.6.2.1, Suppression Pool Average Temperature 3/15 =0.2 Deg f/min: 105 - 77 = 28 deg F: 28/0.2 = 140 min MODIFIED HIGHER

QNUM 070

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.2.13

QUESTION Which of the following lists examples of conditions that require a Clearance Order to be EXCEPTIONAL?

a. freeze seal, relief valve gagging device, work in electrical cubicles that contain backfeed voltages.

b. relief valve gagging device, work in electrical cubicles that contain backfeed voltages, valve that is opened and torqued on its backseat.

c. freeze seal, work in electrical cubicles that contain backfeed voltages, valve that is opened and torqued on its backseat.

d. freeze seal, relief valve gagging device, valve that is opened and torqued on its backseat.

ANSWER a.

REFERENCE OP-AA-109-101, Clearance and Tagging, Rev 0, paragraph 7.1.2, 7.3.3.1, 7.3.4.3.C, 7.3.8.10, 7.3.2.7 and Attachment 2 (page 51).

NEW FUNDAMENTAL

QNUM 071

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.2.28

QUESTION During Core Alterations, the Reactor Operator is required to verify that the SRMs are reading at least ____(1)______ every _____(2)_____.

(1) (2)

a. 3 cps 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b. 3 cps 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

c. 0.7 cps 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

d. 0.7 cps 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

ANSWER b.

REFERENCE QCFHP 0100-01, Master Fuel Handling procedure, Rev 26, pg 8 step E.2 and page 11, step E.17.b.(2)

Technical Specification 3.3.1.2 NEW FUNDAMENTAL

QNUM 072

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.3.4

QUESTION In order to extend the administrative dose control limit for an individual to 3000 mrem TEDE, the individual must request the extension and the request must be approved by the . . .

a. work group supervisor only.

b. work group supervisor and the RP Manager only.

c. work group supervisor and the RP Manager and the Station Manager only.

d. work group supervisor and the RP Manager and the Station Manager and the Site Vice President.

ANSWER b.

REFERENCE RP-AA-203, Rev 2, Exposure Control and Authorization, pg 9 of 12.

NEW FUNDAMENTAL

QNUM 073

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.3.9

QUESTION Operators are preparing to vent the primary containment.

Which of the following can NEVER be used to ensure that the radioactive release rate will remain below the ODCM allowed release rate limit?

a. A calculation provided IAW EP-MW-110-200, Dose Assessment.

b. The absence of annunciator 912-1, E-3, Main Chimney GE Radiation Monitor High-High Radiation.

c. The absence of annunciators 912-1, E-9, or F-9, High Radiation Detected on Eberline Radiation Monitors A or B.

d. A vent recommendation IAW QCCP 1300-01, Drywell & Suppression Chamber Sampling, Venting, & Purging.

ANSWER b.

REFERENCE QCOP 1600-13, Post-Accident Venting of the Primary Containment, Rev 19, pg 1 NEW FUNDAMENTAL

QNUM 074

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.4.12

QUESTION Complete the following sentence:

During transient conditions, the RO (1) immediate operator actions of abnormal procedures from memory (2) the Unit Supervisor.

(1) (2)

a. may NOT perform until directed by

b. may NOT perform until concurred upon by

c. may perform while verbalizing actions being taken to

d. may perform only after verbalizing the actions to be taken to

ANSWER c.

REFERENCE OP-AA-101-111, Roles and Responsibilities of On-Shift Personnel, Rev 0 NEW FUNDAMENTAL

QNUM 075

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL B

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.4.49

QUESTION Unit 2 is operating at 83% power with the following plant conditions existing:

- Bus 25-2 is OOS.

- MCC 28-2 has tripped and is being investigated.

- All expected actions occurred.

- One minute later, APRM 5 FAILED, resulting in an INOP trip.

The NSO noted the appropriate alarms on 902-5, but ONLY light 4 of the RPS solenoid group lights extinguished. Lights 1, 2 and 3 are STILL lit.

The FIRST action that the NSO should take is to . . .

a. depress the A manual scram pushbutton

b. depress the B manual scram pushbutton.

c. bypass APRM 5 and reset the half scram.

d. refer to TS 3.3.1.1 to determine proper actions.

ANSWER b.

REFERENCE QC Bank question 342099 BANK HIGHER

QNUM 076

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 295001 2.4.4

QUESTION Unit 1 is at 100% power following a refueling outage.

When the 1B Recirc MG Set tripped on high current. NO action was taken other than reducing 1A Recirc MG Set to 78% speed. The NSO notes that approximately 10 LPRM Hi lights are coming in and out near the core center at a frequency of about once every second. APRMs do NOT indicate appreciable change.

As Unit Supervisor, what procedure do you enter and what actions do you order?

a. Enter QCOA 0202-04, Reactor Recirc Pump Trip - Single Pump AND insert CRAM rods

b. Enter QCOA 0202-04, Reactor Recirc Pump Trip - Single Pump AND insert a reactor scram

c. Enter QCOA 0400-02, Core Instabilities AND insert CRAM rods

d. Enter QCOA 0400-02, Core Instabilities AND increase Reactor Recirc flow

ANSWER b.

REFERENCE QC Bank question 340140 295001 2.4.4 MODIFIED HIGHER

QNUM 077

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 295003A102

QUESTION Unit 2 was operating at 60% power with a normal electric plant lineup when a transient occurred. The following valid annunciators were received in the order listed:

- 902-8, F3, 4 KV BUS OVERCURRENT

- 902-8, A1, 4KV MAIN FEED BREAKER TRIP

- 902-8, D3, 4KV BUSSES 23/24 LOW VOLTAGE

- 902-8, A7, DIESEL GEN #2 TROUBLE

- 902-8, G8, DIESEL GEN #2 RELAY TRIP The unit supervisor diagnoses the failure as an overcurrent ____(1)______.

To mitigate this event, the unit supervisor orders ______(2)________ .

(1) (2)

a. (1) trip of Bus 23.

(2) establish alternate power to Bus 23-1 IAW QCOP 6500-08, 4KV Bus Cross-Tie Operation.

b. (1) trip of Bus 24.

(2) establish alternate power to Bus 24-1 IAW QCOP 6500-08, 4KV Bus Cross-Tie Operation.

c. (1) condition that locked out Bus 24-1.

(2) Reestablish normal power to Bus 24 IAW QCOP 6500-09, Energizing 4KV Switchgear & Transferring Auxiliary Power.

d. (1) trip of Transformer 21 that deenergized Bus 24.

(2) Verify proper operation of U2 EDG IAW QCOP 6500-02, Diesel Generator 1(2) Startup Procedure.

ANSWER b.

REFERENCE QC Bank Question 339272 Bus 24 has an overcurrent condition based upon, OC alarm, alarm for T21 bkr trip and U2 EDG alarms. The U2 EDG has tripped on OC (186 trip G8).

MODIFIED

HIGHER

QNUM 078

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 295005 2.1.20

QUESTION Unit 1 was operating at 28% of rated power when the following annunciator alarmed:

- 901-7, A-4 TURB TRIPPED OPERATING OIL LOW PRESSURE During the transient, Reactor pressure remained within 900 to 1000 psig, and Reactor water level remained between 15 inches and 38 inches. As Unit Supervisor, you enter procedure

______(1)_______ and _____(2)______ .

(1) (2)

a. (1) QCGP 2-3, Reactor Scram (2) verify all main turbine stop, control, intercept and bypass valves are closed.

b. (1) QGA 100, RPV control (2) follow pressure and level legs.

c. (1) QOA 5600-04, Loss of Turbine Generator (2) verify main turbine bypass valves control reactor pressure.

d. (1) QCOA 5650-01, Malfunction of EHC Pressure Control System (2) reduce power using recirculation flow.

ANSWER c.

REFERENCE QCAN 901-7, A-4 Turb Tripped Operating Oil Low Pressure QOA 5600-04, Loss of Turbine Generator, Rev 23 295005 2.1.20 NEW HIGHER

QNUM 79

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 295018A204

QUESTION Unit 1 was operating at 96% steady state power. The NSO inadvertently closed MO-1-3702 RBCCW to Drywell Supply Isolation Valve. He realized his mistake and just as the valve indicated full closed, he tried to re-open the MO-1-3702. This caused its breaker to trip with MO-1-3702 closed.

When the NSO informs you of this condition as the Unit Supervisor you will . . .?

a. Direct the Unit 1 NSO to stop both Recirc Pumps then scram Unit 1.

b. Dispatch a Non-Licensed Operator to fully open the bypass around MO-1-3702 within 5 minutes or scram Unit 1.

c. Dispatch a Non-Licensed Operator to reset the breaker for MO-1-3702. If the NLO cant reset the breaker to allow reopening MO-1-3702 within 5 minutes, scram Unit 1.

d. Dispatch a Non-Licensed Operator immediately to manually re-open MO-1-3702.

If the NLO cant start to reopen MO-1-3702 within 1 minute, scram Unit 1.

ANSWER a.

REFERENCES Lesson Plan LF-3700 Reactor Building Closed Cooling Water System Loss of both Recirc pumps requires a reactor scram.

NEW HIGHER

QNUM 80

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 295023 2.4.30

QUESTION During refueling in Unit 2, a fuel assembly is dropped in the reactor vessel. Immediate actions taken include manual start of the SBGTS. Radiation levels on the refuel floor slowly increase to 20 mrem/hr general area. Nobody exceeds administrative radiation exposure limits.

How would this be categorized AND when should the NRC be notified of this event?

a. This is categorized as an Unusual Event, the NRC needs to be notified within 15 minutes.

b. This is categorized as an Alert, the NRC needs to be notified within 15 minutes.

c. This is categorized as an actuation of a valid safety system, the NRC needs to be notified within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d. This is considered a Reportable Event (Only), the NRC needs to be notified within 60 days.

ANSWER c.

REFERENCES 10CFR50.72 EP-AA-1006, Radiological Emergency Plan Annex, Rev 22, pgx 3-75, 76 LS-AA-1020, Reportability Reference Manual, Rev 9 295023 2.4.30 NEW FUNDAMENTAL

QNUM 81

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore/Walton

QVAL 1.00

SEC

SUBSORT

KA 295026A202

QUESTION Unit 2 is in Mode 1 with suppression pool initial conditions of:

Suppression pool level at 14' 3" Suppression pool average temperature 70 degrees F.

Subsequently, a relief valve begins to leak past its seat. Suppression pool level increases by 0.2 inches/hr and average suppression pool temperature increases at 10 degree F/hr.

Which suppression pool Tech Spec limit will be reached first (level or average temperature)

AND what is the Tech Spec Bases for that high limit?

a. High average Torus water temperature limits will be reached first.

Basis: to prevent primary containment pressures and temperatures from exceeding maximum allowable values during a DBA LOCA.

b. High average Torus water temperature limits will be reached first.

Basis: to prevent excessive down-comer loads to cause excessive swell during relief valve operations during a DBA LOCA.

c. High Torus water level limits will be reached first.

Basis: to prevent primary containment pressures and temperatures from exceeding maximum allowable values during a DBA LOCA.

d. High Torus water level limits will be reached first.

Basis: to prevent excessive down-comer loads to cause excessive swell during relief valve operations during a DBA LOCA.

ANSWER a.

REFERENCES Tech Spec Bases 3.6.2.1 Suppression Pool Average Temperature Tech Spec Bases 3.6.2.2 Suppression Pool Water Level NEW HIGHER

QNUM 82

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 295028 2.4.41

QUESTION The following plant conditions exist on Unit 1:

- Reactor Coolant Activity 325 µCi/gm I-131 dose equivalent

- Drywell Pressure 4.7 psig and stable

- Reactor Pressure 75 psig and stable

- All MSIVs are closed

- Drywell sprays and drywell cooling have failed

- Drywell temperature is 285 degrees F and increasing very slowly

- Reactor Water level is at -100 inches and slowly increasing

- CRD pumps are the only pumps providing water to the core Based on these conditions, which Emergency Action Level classification would you declare?

a. Unusual Event - FU1

b. Alert - FA1

c. Site Area Emergency - FS1

d. General Emergency - FG1

ANSWER d.

REFERENCES EP-AA-1006 Rev. 19 (12/04) 295028 2.4.41 NEW HIGHER

QNUM 83

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 295007A201

QUESTION After a long operating period, the Unit 1 Reactor was manually scrammed due to steam tunnel temperatures rapidly rising to >200 degrees F. Reactor pressure was cycling between 1115 psig and 1070 psig. In accordance with the pressure leg of QGA 100, RPV Control, you establish a pressure band _____(1)_____ using ___(2)_____ to control Reactor pressure.

(1) (2)

a. below 940 psig ADS valves.

b. between 940 and 1060 psig ADS valves.

c. below 940 psig turbine bypass valves.

d. between 940 and 1060 psig turbine bypass valves.

ANSWER b.

REFERENCES Quad Cities Lesson Plan 1603, Primary Containment Isolation System, pg 3 Quad Cities Lesson Plan 0203, ADS, pg 3 QGA 100 Basis document NEW HIGHER

QNUM 84

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 295014A204

QUESTION Unit 2 was at 35% power. Due to a transient condition, AND a failure of the RPS system to actuate, the reactor was operated with reactor pressure at 750 psig for a short period of time.

Reactor engineering determined that this condition resulted in Minimum Critical Power Ratio (MCPR) being <1.05.

As Unit Supervisor, you realize this condition is a violation of ______(1)______ and you must

_____(2)______ .

a. (1) Safety Limit 2.1.1 (2) Insert all insertable control rods within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b. (1) TS 3.1.1, Shutdown Margin (2) Restore Shutdown Margin within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. (1) Safety Limit 2.1.1 (2) Restore MCPR to within allowable limits immediately.

d. (1) TS 3.1.1, Shutdown Margin (2) Fully insert all insertable control rods immediately.

ANSWER a.

REFERENCES Tech Spec 2.1, & 3.1.1 NEW HIGHER

QNUM 85

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 295032 2.4.7

QUESTION With Unit 1 at full power operation, the Unit 1 Control Room receives the following annunciators:

901-4, A-12, RWCU AREA TEMPERATURE A HIGH 901-4, A-13, RWCU AREA TEMPERATURE B HIGH Reactor pressure, level and power are stable, but attempts to isolate RWCU have failed.

RWCU Heat Exchanger Room Temperature quickly rises to 170 degrees F.

As Unit Supervisor, you . . .

a. reduce reactor power IAW QCGP 3-1, Reactor power operations.

b. enter QGA 100, RPV Control, ONLY, and scram the reactor.

c. Enter QGA 300, Secondary Containment Control, and shutdown the reactor IAW QCGP 2-1, Normal Unit Shutdown.

d. Enter QGA 300, then enter QGA 100, RPV Control to scram the reactor.

ANSWER d.

REFERENCES QCAN 901(2)-4 A-12 RWCU Area High Temperature, Rev 6.

QGA 300 295032 2.4.7 NEW HIGHER

QNUM 86

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2060000 2.1.32

QUESTION Unit 2 is starting up in accordance with QCGP 1-1, following a weekend outage. No work was performed on HPCI, but periodic overspeed testing is scheduled during startup. A Clearance Order, which was placed to allow the Mechanics to prepare HPCI for the overspeed test, is now TEMP LIFTED. The Startup schedule indicates that Reactor pressure should be raised to 155 psig for HPCI overspeed testing. Reactor pressure is presently 136 psig, increasing to 155 psig at 2 psig / minute. The ANSO just brought to your attention, a caution statement in QCGP 1-1:

"IF HPCI / RCIC overspeed testing is to be performed, THEN do NOT allow Reactor pressure to exceed 150 psig until testing is completed."

(1) What Reactor pressure should you direct the ANSO to maintain?

AND (2) What is the basis for the response?

(1) (2)

a. (1) 142 psig.

(2) The caution statement is correct, BUT HPCI IS ALREADY OPERABLE.

b. (1) 155 psig.

(2) The caution statement is correct, BUT HPCI IS ALREADY OPERABLE.

c. (1) 142 psig.

(2) The caution statement is correct, HPCI is NOT OPERABLE and MUST BE MADE OPERABLE before pressure goes above 150 psig.

d. (1) 155 psig.

(2) The caution statement does NOT apply in this case because HPCI does NOT need to be OPERABLE until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AFTER Reactor pressure exceeds 150 psig. The procedure can be REVISED later.

ANSWER c.

REFERENCES QC Bank Question 301983 2060000 2.1.32 BANK HIGHER

QNUM 87

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 211000A205

QUESTION Unit 1 is in Mode 1 and the electrical breaker to the Standby Liquid Control (SBLC) Tank heaters has failed. The SBLC tank initial temperature was 90 degrees F, level was at 3600 gallons and boron concentration (by weight) was 15.5%.

Given these conditions AND that the breaker will NOT be repaired before tank temperature decreases below the minimum value allowed by Technical Specifications, what TS Action statement is applicable AND what MINIMUM TS surveillance requirements must be completed upon return of the heaters to service before the SBLC tank can be declared operable?

Action Statement Surveillance Requirements

a. TS 3.1.7 A SR 3.1.7.2, SR 3.1.7.3, SR 3.1.7.5, SR 3.1.7.9

b. TS 3.1.7.A SR 3.1.7.2, SR 3.1.7.5

c. TS 3.1.7.B SR 3.1.7.2, SR 3.1.7.3, SR 3.1.7.5, SR 3.1.7.9

d. TS 3.1.7.B SR 3.1.7.2, SR 3.1.7.5

ANSWER d.

REFERENCES Technical Specification 3.1.7, Standby Liquid control System.

NEW HIGHER

QNUM 88

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 212000A212

QUESTION Unit 2 is as 75% power. Instrument Maintenance personnel report that Unit 2 (Turbine Control Valve Fast Closure circuit) is faulted and can NOT be aligned and must be replaced.

Given (DWG 4E-XXX), determine:

(1) what Technical Specification Function is impacted by this condition, AND (2) if Technical Specification 3.3.1.1, Action E is applicable.

(1) (2)

a. Turbine Stop Valve - Closure TS NOT applicable

b. Turbine Control Valve - Fast Closure TS NOT applicable

c. Turbine Stop Valve - Closure TS IS applicable

d. Turbine Control Valve - Fast Closure TS IS applicable

ANSWER d.

REFERENCES Technical Specification 3.3.1.1 NEW HIGHER

QNUM 89

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 239002A202

QUESTION You are the Unit 2 Unit Supervisor. The Unit 2 NSO has just informed you that alarm 902-4 F-18, FAILURE OF TARGET ROCK VALVE 3A BELLOWS has just come in. The following plant conditions exist:

Acoustic Monitor Activated alarm.

Tail-pipe Temperature Recorder TRX-260-20 indicates 225 degrees F.

Drywell pressure increasing very slowly.

Torus Temperature increasing very slowly.

Reactor Pressure steady at 975 psig.

Total RCS Leakage is 7.5 gpm.

As the Unit Supervisor which of the following actions should you direct?

a. Cycle Target Rock Valve 2-203-3A control switch between AUTO and MANUAL in an attempt to reseat the valve and if that is unsuccessful the Unit 2 Reactor must be shutdown to MODE 3 with in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 4 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. Cycle Target Rock Valve 2-203-3A control switch between AUTO and MANUAL in an attempt to reseat the valve and if that is unsuccessful start to shutdown the Unit 2 Reactor prior to Torus Temperature reaching 95 degrees F.

c. Do Not attempt to reseat Target Rock Valve 2-203-3A, based on current plant conditions power operation may continue indefinitely.

d. Do Not attempt to reseat Target Rock Valve 2-203-3A, based on current plant conditions the Unit 2 Reactor must be shutdown to MODE 3 with in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

ANSWER d.

REFERENCE QCAN 901(2)-4 F-18, Failure of Target Rock Valve 3A Bellows QCOA 0203-01 Failure of a Relief Valve to Close or Reseat Properly Tech Spec 3.4.3 Safety and Relief Valves Tech Spec 3.4.3 Bases NEW HIGHER

QNUM 090

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 262001 2.1.12

QUESTION Unit 1 is in Mode 1. At 0200 on June 1, DG 1 Circulating Oil Pump develops a motor short and trips. Surveillance Requirement 3.8.1.1 is completed at 0250. Without requiring entry into a TS Condition that requires a plant shutdown and using allowed TS extentions, as Unit Supervisor, what is the LATEST time that you must assure the next completion of SR 3.8.1.1?

a. June 1, by 1000

b. June 1, by 1050

c. June 1, by 1250

d. June 1, by 1300

ANSWER c.

REFERENCE QC Bank question 340803 262001 2.1.12 MODIFIED HIGHER

QNUM 91

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 214000 2.2.33

QUESTION Unit 1 is at 97% power. Control Rod H-10 had just been moved to position 36 per QCOS 0300-01, CRD Exercise procedure, when all position indication was lost due to a faulty connector. No other rods were affected by this failure.

As the Unit Supervisor, which of the following actions should you take to address the failed rod position indication?

a. Enter QCOA 0280-01, RPIS Failure procedure, Reset Reactor Manual Control System, Reduce Reactor Power.

b. Enter QCOA 0280-01, RPIS Failure procedure, Insert Control Rod H-10, Disarm Control Rod Drive mechanism for rod H-10.

c. Reset Reactor Manual Control System, complete QCOS 0300-01, CRD Exercise procedure, then enter QCOA 0280-01, RPIS Failure procedure.

d. Notify the Shift Manager and the Unit 1 QNE, reduce Reactor Power to minimize xenon production, enter QCOA 0280-01 RPIS Failure procedure.

ANSWER b.

REFERENCE QCOA 0280-01 RPIS Failure QCOS 0300-01 CRD Exercise Tech Spec 3.1.3 Control Rod Operability Tech Spec 3.1.3 Bases 214000 2.2.33 NEW HIGHER

QNUM 92

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 239001 2.1.28

QUESTION (1) When is Technical Specification 3.7.7 applicable AND (2) When are the Main Turbine Bypass Valves assumed to function, AND (3) What safety parameter is the Main Turbine Bypass Valves protecting?

(1) (2) (3)

a. $15% RTP Turbine Trip APLHGR

b. $15% RTP Load Reject MCPR

c. $25% RTP ATWS APLHGR

d. $25% RTP Feedwater Controller Failure MCPR

ANSWER d.

REFERENCE Tech Spec 3.7.7 and Tech Spec Bases 3.7.7 239001 2.1.28 NEW HIGHER

QNUM 93

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 290002A204

QUESTION What is one of the RCS Temperature Limits and what is the bases for Tech Spec 3.4.9 RCS Pressure and Temperature (P/T) Limits?

a. RCS Cooldown rates must be # 100 degrees F/Hr so that undetected flaws will NOT propagate and cause non-ductile failure of the reactor coolant pressure boundary, a condition that is unanalyzed.

b. RCS Heat-up rates must be # 100 degrees F/Hr so that pressure stresses in the reactor pressure vessel do NOT cause a non-ductile failure of the reactor pressure vessel as analyzed in the Design Bases Accident analyses.

c. Reactor Vessel flange and Head flange temperatures must be $ 93 degrees F to prevent exceeding the Reactor Vessel stress analyses.

d. The difference between the bottom head coolant temperature and the reactor pressure vessel coolant temperature must be # 125 degrees F so that pressure stresses in the reactor pressure boundary due NOT cause a non-ductile failure of the reactor pressure vessel as analyzed in the Design Bases Accident analyses.

ANSWER a.

REFERENCE Tech Spec 3.4.9 TS Bases 3.4.9 NEW HIGHER

QNUM 94

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 2.1.1

QUESTION During the performance of a special test while at 95% reactor power the 1A Core Spray Pump is placed in Pull-to-Lock. For the special test the Shift Manager has dedicated one NSO as being responsible for restoring the 1A Core Spray pump in the event that it becomes necessary, and hence has determined that the 1A Core Spray pump remains OPERABLE. As the Unit 1 Unit Supervisor you...

a. agree with the Shift Managers operability determination regarding the 1A Core Spray pump and continue with the special test.

b. disagree with the Shift Managers operability determination regarding the 1A Core Spray pump and enter Tech Spec 3.5.1, ECCS-Operating.

c. agree with the Shift Managers operability determination regarding the 1A Core Spray pump and enter Tech Spec 3.3.5.1 ECCS Instrumentation.

d. disagree with the Shift Managers operability determination regarding the 1A Core Spray pump and enter Tech Specs 3.3.5.1 ECCS Instrumentation and 3.5.1 ECCS-Operating.

ANSWER b.

REFERENCE QAP 0300-02, Conduct of Shift Operations, Rev. 66.

2.1.1 NEW HIGHER

QNUM 95

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ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 2.1.19

QUESTION You are the Unit 1 Unit Supervisor during an accident when the Safety Parameter Display System (SPDS) starts displaying a Yellow parameter. What does the Yellow color signify and if the SPDS were to completely fail how long may it be out before the NRC must be notified?

a. Yellow indicates an ALERT condition and if the SPDS is out of service for greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the NRC must be notified.

b. Yellow indicates an ALARM condition and if the SPDS is out of service for greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the NRC must be notified.

c. Yellow indicates an ALERT condition and if the SPDS is out of service for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the NRC must be notified.

d. Yellow indicates an ALARM condition and if the SPDS is out of service for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the NRC must be notified.

ANSWER d.

REFERENCE QCOA 9900-02, Loss of Plant Process Computer (PPC)

LS-AA-1020, Reportability Reference Manual Vol. 1 - Table SAF QOP 9900-102 Operation of Safety Pararmeter Display System Distractor b is not correct because alarm is incorrect.

Distractor c is not correct because 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is incorrect.

Distractor d is not correct because alarm and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are incorrect.

NEW HIGHER

QNUM 96

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 2.2.26 Refueling administrative requirements.

QUESTION During in-vessel fuel movement with the Reactor Mode Switch in the REFUEL position the failure of the (1) interlock would require (2) .

(1) (2)

a. refuel platform fuel grapple to fully retract suspension of all fuel movement.

b. refuel platform position control rod withdraw block insertion AND verification of all control rods fully inserted.

c. refuel platform monorail position suspension of in-vessel fuel movement involving the refuel platform monorail.

d. refuel platform frame mounted hoist control rod withdraw block insertion OR verify all control rods are fully inserted.

ANSWER b.

REFERENCE Tech Spec 3.9.1 Refueling Equipment Interlocks NEW MEMORY

QNUM 97

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.3.2

QUESTION In accordance with corporate Dose Equalization policy, the Unit Supervisor should maintain individual Non-Licensed Operators within the recommended band of ____(1)_____ of the group mean dose utilizing _____(2)______.

(1) (2)

a. + 100 mrem a three-year rolling average.

b. + 200 mrem a three-year rolling average.

c. + 100 mrem the yearly department cumulative dose list.

d. + 200 mrem the yearly department cumulative dose list.

ANSWER b.

REFERENCE RP-AA-400-1002, Dose Equalization, Rev 0.

NEW HIGHER

QNUM 98

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 2.3.6

QUESTION What MINIMUM requirements must be met to discharge the River Discharge Tank (RDT) to the river if the Radwaste Liquid Effluent Line Radiation Monitor Panel 2212-948 is inoperable?

a. None, the River Discharge Tank may NOT be discharged until the Radwaste Liquid Effluent Line Radiation Monitor Panel 2212-948 is operable.

b. One RDT sample, one qualified station individual performs discharge calculation, one qualified radwaste operator performs valve alignment, AND previous actions logged.

c. Two independent RDT samples, two independent station personnel verify discharge calculation, one qualified radwaste operator performs valve alignment, AND previous actions logged.

d. Two independent RDT samples, two independent station personnel verify discharge calculation, two qualified radwaste operators perform valve alignment, AND previous actions logged.

ANSWER d.

REFERENCE QOP 2000-24 & QOP 2000-25 ODCM, Chapter 12 NEW MEMORY

QNUM 99

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Moore

QVAL 1.00

SEC

SUBSORT

KA 2.4.28

QUESTION This question has been redacted due to its security-related content.

REFERENCE NEW HIGHER

QNUM 100

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 2007/06/04

FAC 254

RTYP BWR-GE3

EXLEVEL S

EXMNR Walton

QVAL 1.00

SEC

SUBSORT

KA 2.4.46

QUESTION Given the initial conditions on Unit 1:

- Reactor scram has occurred, all rods in,

- Reactor water level at -55 inches and lowering rapidly,

- Reactor pressure 700 psig and lowering slowly,

- Drywell pressure 2.7 psig and rising slowly

- RCIC pump is being started,

- No other high pressure injection sources are available,

- Annunciator 901-3, B-13, Automatic Blowdown Timer Start has just alarmed.

As Unit Supervisor, you have just determined that you can NOT hold level above -59 inches.

You order the NSO to inhibit ADS. The NSO places the ADS Inhibit switch in INHIBIT.

Annunciators ...

- 901-3, G-14, Auto Blowdown Inhibit is EXTINGUISHED

- 901-3, B-13, Auto Blowdown Timer Start is LIT To prevent ADS blowdown, you could order ..

a. Secure low pressure ECCS pumps.

b. Place individual ADS valve control switches in OFF.

c. Momentarily (<1 second) depress the ADS Timer Reset pushbutton.

d. Spray the drywell to lower drywell pressure below the reset pressure point.

ANSWER a.

REFERENCE QCAN 901(2)-3 G-14, Auto Blowdown Inhibit Rev. 3 QCAN 901(2)-3 B-13, Auto Blowdown Timer Start, Rev 6 Lesson Plan 0203, ADS, pgs 4, 8, 13-14.

NEW HIGHER

END

ML072920420

Text

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