Sro Excore Ni Rcs Inst Rod Control Wk5

Front 1

The source range NIS detectors operate in the _____________region of the gas filled detector characteristic curve. A. proportionalB. ionizationC. geiger-muellerD. recombination

Back 1

A

Front 2

The level trip switch on the source range drawer is used to: A. Allow energizing a source range detector in the event the P-6 permissive fails.B. Block the source range flux doubled actuation during reactor startup.C. bypass the source range high flux reactor trip for maintenance or testing.D. Trip the associated source range high flux bistable in the event of a source range channel failure.

Back 2

C

Front 3

Gamma compensation is accomplished for an Intermediate Range detector in which of the following methods? A. The inner and outer cans are electrically grounded to provide each other a common reference voltage to compensate for the gamma radiation induced ionization in both cans.B. The effects of the gamma induced current are electrically canceled by the use of compensating voltage applied to the inner can only, and subsequent subtractions of that resulting current from the outer can current.C. The compensation circuit screens the output of the inner can to allow only pulses of sufficient magnitude to pass and be electrically compared to the outer can neutron and gamma current.D. The inner and outer cans are of different surface areas which have been designed to compensate for the differing volume ionization coefficients. This allows the resulting current to be representative of the neutron current only.

Back 3

B

Front 4

One excore nuclear instrumentation system channel qualified to withstand a post-accident containment environment is: A. Source Range N31B. Power Range N41C. Intermediate Range N36D. Source / wide range N61

Back 4

D

Front 5

In the gamma-metrics post-accident detectors, neutrons are absorbed by _________ atoms which ________________ and release energy. A. boron / fissionB. boron / become excitedC. uranium / fissionD. uranium / become excited

Back 5

C

Front 6

With the plant in Mode 5 and rods capable of withdrawal, what will occur if the instrument fuse(s) blow on a source range channel?The source range high flux trip: A. will actuate; the trip will be able to be bypassed at the source range drawer.B. will not actuate; the trip will be able to be bypassed at the source range drawer.C. will not actuate; the trip will not be able to be bypassed at the source range drawer.D. will actuate; the trip will not be able to be bypassed at the source range drawer.

Back 6

A

Front 7

Reactor power is being maintained at 6% prior to placing the Main Turbine on-line. Intermediate Range (IR) channel N-35 is in TRIP BYPASS, with all required bistables tripped for troubleshooting due to a failure which occurred just after entering Mode 1. What (if any) effect occurs if N-35 Control Power is lost in this condition? A. The reactor trips on IR High.B. An IR compensating voltage alarm is generated.C. Both source range detectors energize.D. IR voltage failure alarm is generated.

Back 7

A

Front 8

The reactor is at critical at 1.0 E-8 amps and stable. Inverter NN11 output breaker trips open causing a loss of 120 VAC (Instrument Bus NN01).For this condition, what reactor trip signal is generated first? A. PZR High Pressure.B. PZR Low Pressure.C. IR Channel Bistable Trip.D. S/G Lo-Lo Level.

Back 8

C

Front 9

A power escalation is in progress with reactor power currently at 8%.A reactor trip would occur if which ONE channel of Nuclear Instrumentation were to fail high? A. Power rangeB. Intermediate rangeC. Post-accidentD. Source range

Back 9

B

Front 10

A secondary calorimetric determines secondary power from: A. steam flow and feedwater flowB. steam flow, feedwater flow, and steam pressure.C. steam flow onlyD. steam flow, feedwater flow, steam pressure, and feedwater temperature.

Back 10

D

Front 11

In the excore nuclear instrumentation system, "Axial Flux Difference" is defined as the difference in normalized flux signals between: A. any of the power range upper detectors.B. the top and bottom halves of a power range detector.C. the average of the upper and lower power range detectors.D. any of the power range lower detectors.

Back 11

B

Front 12

Given the following power range data:Channel N-41 N-42 N-43 N-44Upper detector 51 ma 49ma 57ma 56ma Lower detector 53ma 54ma 56ma 54maWhich one of the following is the Quadrant Power Tilt Ratio? A. 1.019B. 1.032C. 1.070D. 1.051

Back 12

C

Front 13

What are required TS Actions if one required Intermediate Range Neutron Flux channel becomes inoperable in Mode 1 above P-6 (interlock) and below P-10 (interlock)? A. Place the unit in Mode 3 within 6 hours.B. Verify interlocks in the required state within 1 hour.C. Immediately suspend operations involving positive reactivity additions.D. Exit the Mode of Applicability within 24 hours.

Back 13

D

Front 14

Using the reference provided, what are the required TS Actions if both required Intermediate Range Neutron Flux channels become inoperable in Mode 1 while above P-6 (interlock) and below P-10 (interlock)? A. Place the unit in Mode 3 within 6 hours.B. Verify interlocks in the required state within 1 hour.C. Exit the Mode of Applicability within 24 hours.D. Establish operation below the P-6 interlock within 2 hours.

Back 14

D

Front 15

The primary pressure boundary between the reactor coolant system and the movable incore detector system during normal operations, is the high pressure _________________. A. swagelock seal at the seal table.B. swagelok seal at the vessel head.C. conoseal at the seal table.D. conoseal at the vessel head.

Back 15

A

Front 16

The plant is at 80% power and the NPIS computer is out-of-service. Use the following information to calculate QPTR.Present NIS detector current (micro amps) N41 N42 N43 N44Upper 156 160 155 165What is the maximum Upper Quadrant Power Tilt Ratio? A. 1.037B. 1.035C. 1.026D. 1.015

Back 16

D

Front 17

The plant is at 80% power and the NPIS computer has shown a Quadrant Power Tilt greater than 1.02. Use the following information to calculate QPTR.100% power 0 AO currents (micro amps) N41 N42 N43 N44 AVGTop 227.6 233.7 223.7 234.4 229.9Bottom 218.5 233.7 232.8 232.9 229.5Normalization factors for each detector N41 N42 N43 N44Top 0.990 1.017 0.973 1.020Bottom 0.952 1.018 1.014 1.015Measured NIS current (micro amps) N41 N42 N43 N44Top 182 187 179 188Bottom 185 187 186 186What is the value and location of the tilt? A. Upper, 1.025B. Lower, 1.024C. Lower, 1.044D. Upper, 1.041

Back 17

C

Front 18

The plant is at 80% power and the NPIS computer shows a Quadrant Power Tilt in excess of 1.02.Use the following information to calculate QPTR.100% power 0 AO currents (micro amps) N41 N42 N43 N44 AVGTop 227.6 233.7 223.7 234.4 229.9Bottom 218.5 233.7 232.7 232.9 229.5Normalization factors for each detector N41 N42 N43 N44Top 0.990 1.017 0.973 1.020Bottom 0.952 1.018 1.014 1.015Measured NIS current (micro amps) N41 N42 N43 N44Top 180 183 179 185Bottom 175 187 186 186Does the calculation support the computer? A. No, 1.005B. Yes, 1.029C. No, 1.012D. Yes, 1.022

Back 18

C

Front 19

At 80% power the NPIS computer shows Quadrant Power Tilt in excess of Tech. Spec. limits. Use the tables below when calculating QPTR.100% power 0AO currents (micro amps) N41 N42 N43 N44 AVGTOP 227.6 233.7 223.7 234.4 229.9BOTTOM 218.5 233.7 232.8 232.9 229.5Normalization factors for each detector N41 N42 N43 N44 TOP 0.990 1.017 0.973 1.020BOTTOM 0.952 1.018 1.014 1.015Measured NIS current (micro amps) N41 N42 N43 N44TOP 182 187 188 188BOTTOM 175 187 186 186What is the maximum calculated Upper Quadrant Power Tilt Ratio? A. 1.037B. 1.029C. 1.005D. 1.009

Back 19

A

Front 20

Which statement is true regarding RCS Loop Level Instruments? A. BB LI-54A and BB LI-54B are Cold Calibrated level indicators that tap into the hot leg of loop one and the liquid space of the pressurizer.B. BB LI-54A and BB LI-54B are Hot Calibrated level indicators that tap into the hot leg of loop one and the liquid space of the pressurizer.C. BB LI-54A and BB LI-54B are Hot Calibrated level indicators that tap into the hot leg of loop one and the vapor space of the pressurizer.D. BB LI-54A and BB LI-54B are Cold Calibrated level indicators that tap into the hot leg of loop one and the vapor space of the pressurizer.

Back 20

D

Front 21

A break has occurred in one of the Reactor Vessel Level Indication System (RVLIS) lines outside Containment.What will this leak consist of and how will it be isolated? A. RCS water and the air operated Containment isolation valves close automatically.B. Demineralized water and the motor operated Containment isolation valves close automatically.C. Demineralized water and the hydraulic sensor closes with RCS pressure.D. RCS water and the hydraulic isolator closes with RCS pressure.

Back 21

C

Front 22

The unit is in Mode 3. S/G "A" Narrow Range Water Level - Low Low instrument (Channel 4) is declared inoperable at 0400.What are the Technical Specifications that are entered and the required TS Actions? A. Enter the Actions of TS 3.3.2 only. Place the inoperable channel in trip by 1000.B. Enter the Actions of TS 3.3.2 only. Restore the inoperable channel to OPERABLE status by 1000.C. Enter the Actions of TS 3.3.1 and TS 3.3.2. Restore the inoperable channel to OPERABLE status by 1000.D. Enter the Actions of TS 3.3.1 and TS 3.3.2. Place the inoperable channel in trip by 1000.

Back 22

A

Front 23

The unit is operating at 100% RTP. S/G "A" Narrow Range Water Level Low Low Instrument (Channel 4) is declared inoperable at 0400. - At 0600, the inoperable channel is placed in trip. Repair time estimate is 24 hours. - At 0800, S/G "B" Narrow Range Water Level - Low Low (Channel 3) is declared inoperable.When must S/G "B" Narrow Range Level instrument channel be placed into trip without requiring entry into a TS shutdown? A. 1200B. 1600C. 1000D. 1400

Back 23

D

Front 24

What set of auctioneered inputs goes to the Subcooling Margin Monitors? A. Low WR RCS or NR PZR pressure and high temperature.B. Low WR RCS pressure and low temperature.C. High WR RCS pressure and high temperature.D. High WR RCS or NR PZR pressure and low temperature.

Back 24

A

Front 25

The plant is operating at full power when a RCS Loop 1 wide range TCOLD Resistance Temperature Detector (RTD) fails HIGH.What effect will this event have on indicated subcooling on the "B" Train Core Subcooling Monitor? A. Large decrease since the Subcooling Monitor uses the highest reading wide range RTD or core exit thermocouple.B. Small decrease since the Subcooling Monitor uses the average of the wide range RTD's and the core exit thermocouples.C. No effect since the Subcooling Monitor is bypassed with the reactor trip breakers closed.D. No effect since only core exit thermocouples provide input.

Back 25

A

Front 26

The plant is at 100% power. STS CR-001, SHIFT LOGS FOR MODES 1, 2 & 3, readings for RCS flow are: BB FI-414 98% BB FI-434 98% BB FI-415 98% BB FI-435 99% BB FI-416 99% BB FI-436 99% BB FI-424 99% BB FI-444 97% BB FI-425 92% BB FI-445 99% BB FI-426 99% BB FI-446 96%What, if any, action is required? A. Contact Reactor Engineering and refer to T.S. 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits.B. Declare BB FI-425 inoperable and trip its bistable within six hours.C. Declare BB FI-425 inoperable and trip its bistable within one hour.D. Readings are acceptable, no action required.

Back 26

B

Front 27

Indication of the failure of a power range channel due to an interruption or loss of power to the power range cabinet would be: A. Main control board alarm for a delta flux out-of-band will be generated.B. The protective bistables for that channel will become inoperable and generate a reactor protection General Warning alarm.C. A 1/4 power range rod stop (C-2) will be generated preventing auto or manual rod withdrawal.D. Indication from the affected channel will indicate 100% scale or 100% power.

Back 27

C

Front 28

The Rod Cluster Control Assemblies consist of rodlets made of silver-indium-cadmium (Ag-In-Cd). What prevents corrosion of this neutron absorbing material? A. The Ag-In-Cd is sealed inside stainless steel tubes.B. The Ag-In-Cd is clad with Inconel.C. Reactor Coolant System temperature is maintained less than 650?F.D. Slightly acidic reactor coolant even with low boric acid concentration.

Back 28

A

Front 29

A reactor startup is in progress with Control Bank "B" being withdrawn. At 135 steps on Control Bank "B", Control Bank "C" begins stepping out.What caused this condition? A. Logic cabinet thumbwheel switch S1 is set for 135.B. Logic cabinet thumbwheel switch S3 is set for 250.C. Power supply cabinet SF110DL Off-Hold-Latch switch is on.D. DC hold supply cabinet switch S-1 is set to off.

Back 29

B

Front 30

The plant is at steady-state with reactor power at 90%. All systems are operating normal with the rod control system in automatic. Without warning, the rods begin to step. Shortly thereafter, Tavg begins to increase above Tref which remains constant. Pressurizer pressure and level begin to increase.These symptoms are consistent with which of the following? A. PZR pressure control system failureB. Main Turbine/Generator load increaseC. Continuous rod withdrawalD. Continuous rod insertion

Back 30

C

Front 31

If the Rod Control CTRL Startup Pushbutton was inadvertently pressed which caused a "Reset" while operating.Which ONE of the following components in the Rod Control System would NOT have to be restored to the proper setting? A. Bank Overlap unitB. Group step countersC. Master CyclerD. P-A converter

Back 31

C

Front 32

The plant is the following condition:* Reactor Power 75%* RCS Pressure 2235 psig* Generator Output 880 MWe* RCS Tavg 5800F* RCS Boron 680 ppm* Control Bank "D" 180 steps* BAT concentration 7000 ppmRod control is in automatic and a VCT makeup occurs with boric acid flow controller potentiometer set to 5.83 turns.What parameter change will be higher than its pre-event value? A. RCS TemperatureB. Reactor PowerC. Control Bank "D" height.D. RCS Pressure

Back 32

C

Front 33

With 5% reactor power and Tavg 20F below T-ref, automatic rod control will not restore Tavg within 1.50F of T-ref. Why? A. The IR Rod Stop has not yet been blocked, inhibiting rod withdrawal.B. Rod control doesn't have a value for T-ref until the turbine is loaded.C. Turbine impulse pressure is not sufficient to clear a rod stop.D. The Tavg/T-ref mismatch is still within the dead band.

Back 33

C

Front 34

The unit is at 50% power with rod control in manual with reactor power and turbine load stable.If T-avg is 5660F when rod control is placed in automatic, what rod speed is indicated? A. 8 steps per minuteB. 0 steps per minuteC. 72 steps per minuteD. 36 steps per minute

Back 34

C

Front 35

The plant is at 100% power with all rods at 229 steps. The rod control bank selector switch is in automatic. An out demand signal with the rod speed indicator reading 48 SPM occurs for 10 seconds.Describe the resulting rod control system status. A. Control Bank D Group 1 Step Counter at 232.Control Bank D Group 2 Step Counter at 231 or 232.Control Bank D Group 1 rods at 231.Control Bank D Group 2 rods at 231.B. Control Bank D Group 1 Step Counter at 237.Control Bank D Group 2 Step Counter at 237.Control Bank D Group 1 rod at 231.Control Bank D Group 2 rods at 231.C. Control Bank D Group 1 Step Counter at 299.Control Bank D Group 2 Step Counter at 229.Control Bank D Group 1 rod at 229.Control Bank D Group 2 rods at 229.D. Control Bank D Group 1 Step Counter at 232.Control Bank D Group 2 Step Counter at 231 or 232.Control Bank D Group 1 rod at 232.Control Bank D Group 2 rods at 231 or 232.

Back 35

A

Front 36

The plant is at 100% power with all rods at 229 steps. Rod control is in automatic. During a surveillance procedure, an I & C technician incorrectly installs a transmitter simulator in a T avg circuit that is not in test. The loop's T-avg signal drops the equivalent of five degrees.What is the initial effect on the rod control system and associated indications? A. Temperature error meter indicates minus five degrees; Rod speed meter indicates 72 SPM; Control Bank D rods move out.B. Temperature error meter indicates zero degrees; Rod speed meter indicates 72 SPM; Control Bank D rods move in.C. Temperature error meter indicates minus five degrees; Rod speed meter indicates 8 SPM; Control Bank D rods do not move.D. Temperature error meter indicates zero degrees; Rod speed meter indicates 8 SPM; Control Bank D rods do not move.

Back 36

C

Front 37

The plant is at 100% power steady state with the Rod Control System in manual. The reactor operator has just completed withdrawing Bank D rods.* Step Counter SC CB-D1 reads 233 steps* Step Counter SC CB-02 reads 232 steps* ALR 00-82F "Bank D Full out Rod Stop" alarms* NPIS agrees with step counters* P/A converter indicates Bank D rods at 233 stepsSelect from the following the response which correctly describes the above conditions. A. System indications are consistent with anticipated plant conditions and operator response can proceed IAW ALR 00-82F.B. Group 1 rods are at 231 steps actual and Groups 2 rods are at 230 steps actual as Group 1 always leads Group 2.C. C-11 has malfunctioned and should have prevented demand from exceeding 232 steps on Group 1 rods.D. Control Bank D Group Step Counter SC CB-02 is reading incorrectly and must always agree with the P/A converter.

Back 37

A

Front 38

Due to a loss of NN01, Rod Control will be affected by which component failure? A. NI-41 Failed High.B. AC PT-505 Failed Low.C. BB LI-459 Failed Low.D. LOOP 1 T-hot Failed High.

Back 38

B

Front 39

The following conditions exist:* A blown fuse causes one C Control Bank rod to drop* The crew is recovering the rod IAW OFN SF-011, REALIGNMENT OF DROPPED ROD(S) AND CONTROL ROD MALFUNCTIONS * During rod withdrawl, the backup power supply to the Control Cabinets is lost.* ROD CONTROL NON-URGENT FAILURE annunciator is LIT* The IN-HOLD-OUT switch is in the OUT positionWhat (if any) affect does this failure have on rod recovery? A. Recovery is unaffected.B. Rod motion OUT stops.C. Rod motion in either direction is inhibited.D. The reactor trips on negative rate.

Back 39

A

Front 40

The plant is operating at full power when the supply breaker to 480 VAC Load Center PG19 opens. What effect will this have on the rod control system? A. A Power Cabinet Urgent Failure alarm and loss of the ability to move rods in Auto or Manual Sequential modes.B. Two reactor trip breakers will open but the reactor will not trip.C. Annunciator alarms only.D. The affected rod control power cabinets will swap to their backup power source and continue to operate normally.

Back 40

C

Front 41

> A. Rods will insert until the power mismatch circuit output integral decays.B. Rods will insert until power mismatch circuit deviation causes rod to maintain Tave at no-load setpoint.C. Rods will continuously insert until manual is selected on rod control.D. Rod control is not affected by a HIGH failure of Tcold.

Back 41

C

Front 42

The Reactor is at 100% power with the Rod Control System in automatic. The individual NI's read as follows:* N41 99%* N42 101%* N43 100%* N44 100%PR channel N41 abruptly fails downscale (low) due to an amplifier malfunction. Select the statement that correctly describes the effect of this failure. A. Rods step out because of the Rod Control power mismatch circuit.B. Rods do not respond automatically.C. Rods step in at 72 steps per minute.D. Rods insert due to a high negative rate reactor trip.

Back 42

B

Front 43

Turbine load is at 600 MWe (50% reactor power), and the highest indicated RCS Tave is 568.5oF. With The Rod Control System in AUTO, in what direction and speed should the control banks should be moving? A. Outward at approximately 16 steps per minuteB. Inward at approximately 16 steps per minuteC. Inward at approximately 8 steps per minuteD. Outward at approximately 8 steps per minute

Back 43

A

Front 44

The plant is operating at 100% power steady state with all control systems in automatic. The operators note that rod control bank D starts stepping in intermittently at 8 steps/minute.Which of the following is a possible cause for this rod motion? A. VCT automatic makeup has occurred with the makeup boric acid concentration greater than the RCSB. Emergency borate valve has inadvertently (failed) partially openC. An unborated mixed bed demineralizer has been recently placed in serviceD. Turbine first stage pressure transmitter PT-506 is failing high

Back 44

C

Front 45

Generator output is 780 MW and stable. Reactor power is 75% and slowly increasing. Tavg is 5800F and increasing slowly. (Assume turbine control is on Load Set)What could cause these indications? A. Xenon oscillation.B. Inadvertent boration.C. Uncontrolled rod withdrawal.D. Main Steam leak.

Back 45

C

Front 46

The following conditions exist:* Tavg - 590?F* Tref - 586.5?F* Rods in MANUALIf rods are now taken to AUTO, what will happen? A. Rods will step outward at 40 steps per minuteB. Rods will step inward at 24 steps per minuteC. Rods will step inward at 40 steps per minuteD. Rods will step outward at 24 steps per minute

Back 46

B

Front 47

The plant is at 70% power when control rods are inserted for delta-I control. Control Bank D is at 208 steps when rod H-8 drops to 90 steps from a blown moveable coil fuse.What action must be taken as a result? A. Be in Hot Standby within six hours.B. Determine shutdown margin within one hour and be in Hot Standby within six hours.C. Within one hour restore the rod to within 12 steps of its group step counter.D. Within one hour restore the rod to within 12 steps and be in Hot Standby within the next six hours.

Back 47

C

Front 48

Reactor power is at 8% when a Loss of Condenser Vacuum occurs. Tavg is 5620F and slowly increasing. The Motor Driven Startup Feed Pump is started to supply feed water as a result.What action could be taken to stabilize Tavg and possibly avoid a reactor trip? A. Adjust SG ARVs to 1100 psig and verify automatic operation.B. Manually control SG ARVs and maintain 1092 psig.C. Manually control Steam Dumps and modulate the cooldown valves.D. Drive control rods to reduce reactor power to approximately 1%.

Back 48

D

Front 49

The following conditions exist:* Reactor at 75% power* Rod control in AUTOMATIC* PR NIS readings: N-41 = 76%; N-42 = 75%; N-43 = 75%; N-44 = 75%* Channel N-42 instantaneously fails LOW* NO operator action is takenWhat describes the control rod system response to these conditions? A. Control rods will NOT drive in until the temperature mismatch equals the power mismatch; then Tavg will stabilize at a lower level.B. Control rods will drive out until the power mismatch circuit has timed out; then reactor power will stabilize at a higher value but Tavg will remain constant.C. Control rods will drive in at maximum rate until C-5 blocks control rod motion or a reactor on low Pressurizer pressure occurs.D. Control rods will NOT move because the auctioneered high nuclear power is used as the input for the power mismatch circuit.

Back 49

D

Front 50

One rod in Control Bank "D" has dropped, the cause has been corrected, and the Control Room is ready to retrieve that rod.How is the correct bank overlap maintained when pulling the dropped rod out? A. The lift coil disconnect switches for the non-affected rods in the bank are placed in the disconnected position.B. By selecting the rod bank Auto/Man selector to the bank with the dropped rod.C. The P/A converter is allowed to count and then is reset after the rod has been restored to the correct height.D. The P/A converter Auto-Manual switch is held in manual to keep the P/A converter from counting.

Back 50

D

Front 51

The following plant indications exist:* RCS Tavg decreasing* Annunciator 00-081B, ROD AT BOTTOM, is lit* Control Bank "D" is stepping outward in automatic * Main generator MWe is stableWhat is the most likely malfunction causing this perturbation? A. Inadvertant borationB. Secondary steam breakC. DRPI General WarningD. A dropped rod

Back 51

D

Front 52

The plant is operating at equilibrium 100 percent power level at beginning of life with all control rods fully withdrawn. If the control rods are partially inserted, the axial neutron flux will shift toward _____________ of the reactor. A. the topB. the bottomC. both the top and the bottomD. the middle

Back 52

B

Front 53

At 75% power steady state conditions the Reactor Operator reports control rods are stepping outward in AUTOMATIC. The operator places the rods in MANUAL and rod motion stops. What is a possible cause of this rod motion? A. A Loop T-hot failing high.B. A Loop T-cold failing high.C. First Stage Impulse, AC PT-505 failing high.D. Power range channel NI-42 failing high.

Back 53

C

Front 54

Maintenance of control rods high in the core helps ensure that the resulting axial flux distribution prevents: A. excessive power defect.B. high local power level peaks.C. loss of shutdown margin.D. flux hardening at the core periphery.

Back 54

B

Front 55

> A. radial power distribution in the coreB. quadrant (azimuthal) power distribution in the coreC. axial power distribution in the coreD. total xenon reactivity in the core

Back 55

C

Front 56

The unit is in Mode 1 at 100& power with Rod Control in automatic. Which of the following conditions could cause a direct input to the Reactor Control Unit of the Rod control System to move the Control Rods? A. A steam leak develops on the turbine impulse pressure transmitter (PT-505) sensing lineB. Steam header pressure transmitter (PT-507) is manually isolatedC. A steam leak develops on a Main Steam line pressure transmitter sensing lineD. Feedwater pump discharge header pressure transmitter(PT-508) is manually isolated

Back 56

A

Front 57

During operation at 100% power with all Control Rods indicating in the Full-out position, the "ANY CONTROL ROD BANK at LO-LO LIMIT" alarm is received The probable cause for this alarm is: A. N41 failed to 0%B. Tavg channel failed to 530oFC. OT delta T channel failed to 150%D. P/A Converter malfunction

Back 57

D

Front 58

Which ONE of the following is NOT a correct statement concerning the Control Rod Bank Select Switch when going from AUTO to Control Bank D position? A. Bank D withdrawal beyond 228 steps blockedB. Rod Control In-Hold-Out switch is now enabled C. Bank overlap unit is locked outD. Rod speed changes to 48 steps per minute

Back 58

A

Front 59

The plant is in Mode 1 with the NPIS computer inoperable. Reactor power is being raised to 100% by nuclear instrumentation following a refueling outage. An OT delta T ROD STOP alarm (ANN 82B) is received and no runback occurs. Power range NIs indicate 98%, and generator load is 1205 MWe.In addition to stopping generator loading, what actions are required? A. Reduce turbine load and perform STS RE-009, HEAT FLUX HOT CHANNEL FACTOR MEASUREMENT.B. Verify deltaT power is less than or equal to 100% once per hour until NPIS is restored.C. Ensure deltaT power is less than or equal to 100% and perform a power range calorimetric.D. Reduce power to 80% and perform a power range calorimetric.

Back 59

C

Front 60

All control banks are fully inserted, Control Bank "A" is withdrawn 50 steps with the bank selector switch positioned to CB "A". The selector switch is then placed in "MANUAL" and rods are withdrawn.What is Bank "A" rod height when Control Bank "B" starts to move? A. 113 stepsB. 115 stepsC. 163 stepsD. 165 steps

Back 60

D

Front 61

Why do we overlap control rod banks? A. Reduces boric acid needed for chemical shim control.B. Minimizes burnable poison required by the fuel.C. Ensures moderator temperature coefficient is negative.D. Ensures sufficient negative reactivity addition on rod demand.

Back 61

D

Front 62

To RAPIDLY reduce power from 100% to 80% with a continuous manual rod insertion with the following conditions: Initial Rod Height 229 steps Boron Cb 950 ppm Xenon No change Boron No change Core Burnup 3000 MWD/MTUHow long will rod motion be required? A. 0.5 minutesB. 4 minutesC. 2.5 minutesD. 1.5 minutes

Back 62

C

Front 63

During a power escalation following a reactor startup, you receive an intermediate range rod block (C-1) Which ONE of the following would have allowed you to block this rod stop? A. P-6B. P-10 and P-13C. P-7D. P-10

Back 63

D

Front 64

The following plant conditions exist:* No operator actions have been taken* Core life is near EOL* Power level is 80% and increasing* Tave is increasing* Containment pressure and temperature are normal* Pressurizer pressure is normal* All systems are in normal modeWhich ONE of the following can cause these indications? A. Partial loss of feedwater heatingB. Steam leak outside containmentC. Slow closure of a MSIVD. Continuous rod withdrawal

Back 64

D

Front 65

Which of the following Control Rod Stops requires only one channel to exceed its setpoint to stop all control rod withdrawal? A. Power Range High FluxB. Over power delta TC. Over temperature delta TD. Both A and B

Back 65

A

Front 66

The following events occur:* Reactor Power @ 90%* All control systems in automatic* Control bank D @ 215 steps* The rod position P-A converter has failed as is* The plant experiences a loss of a main feedwater pump* A turbine runback occurs and turbine load stabilizes at 600 MWeWhich ONE of the following describes the response of the ROD BANK LO-LO LIMIT annunciator? A. Does not annunciate until rods are 10 steps above the insertion limitB. Does not annunciate throughout the transientC. Does not annunciate until Control bank C begins to moveD. Does not annunciate until rods are at the insertion limit

Back 66

B

Front 67

There are several factors that affect a critical rod position determination.What factor would result in an INCREASE of an ECP rod height? A. Tavg at startup changes from 5570F to 5510F.B. RCS pressure at startup changes from 2235 psig to 2200 psig.C. Critical boron concentration changes from 800 ppm to 950 ppm.D. Startup time after a trip from 100% power increases from 15 hours to 25 hours.

Back 67

C

Front 68

A reactor is at 50 percent power, steady state, and the rods are withdrawn 1 percent of full rod travel. Assuming no further operator or automatic actions, what will the condition of the reactor be after the power transient has terminated? A. Power will not be changed significantly. Tave will decrease.B. Power will not be changed significantly. Tave will increase.C. Power will decrease significantly. Tave will decrease.D. Power will increase significantly. Tave will increase.

Back 68

B

Front 69

What are the Reactor Coolant System loop operability requirements if the Rod Control System is capable of rod withdrawal in Mode 3? A. Two loops are required to be OPERABLE with both loops in operation.B. Three loops are required to be OPERABLE with at least two loops in operation.C. Only one loop is required to be OPERABLE and in operation.D. Two loops are required to be OPERABLE with at least one loop in operation.

Back 69

A

Front 70

A reactor startup is being performed and criticality occurs with Annunciator 81C, ROD BANK LOLO LIMIT, not cleared. Rod bank B step counter and DRPI indicate the bank is withdrawn 140 steps.What is the concern in this situation? A. Axial flux difference.B. Shutdown margin.C. Heat flux hot channel factor.D. RIL computer is INOPERABLE.

Back 70

B

Front 71

The crew is recovering a dropped rod using OFN SF-011. When the RO starts withdrawing the dropped rod, annunciator 79A (ROD CTRL URG FAIL) alarms.What action would be appropriate for the RO to perform? A. Continue rod withdrawal the alarm pertains to auto rod control.B. Continue rod withdrawal, the alarm is on the cabinet with lift coils open.C. Release the IN-HOLD-OUT switch.D. Release the IN-HOLD-OUT and reset the alarm on RL003.

Back 71

B

Front 72

The unit is at 80% power with rods in manual. Rod position for shutdown Bank E rod D-8 is inoperable. While increasing load to 100% the following alarms are received.* Rod position indication (RPI) urgent failure annunciator alarm.* Rod bottom for H-8 in control Bank D.* General Warning for H-8 in control Bank D.* RPI urgent failure.* RPI Data A and B failure.What action should be taken as a result? (Assume Reactor Power and Tavg are stable) A. Determine the position of rods D-8 and H-8 every eight hours using the moveable incore detectors.B. Emergency borate until SDM is satisfied.C. Restore rods D-8 and H-8 to Operable status within 72 hours or be in Hot Standby within the next six hours.D. Within one hour, take action to be in Hot Standby within the next six hours per T.S. 3.0.3.

Back 72

A

Front 73

The plant is at 100% power when RPI NON URG ALARM, 00-80B, is received. DATA A FAILURE 1 2 3 lights are on.What Technical Specification action is appropriate? A. Restore DRPI to operable within 72 hours.B. Be in Hot Standby within six hours.C. Use moveable incore's to determine rod position within eight hours.D. Verify half accuracy is maintained.

Back 73

C

Front 74

The plant is at 100% power steady state with the Rod Control System in manual. The reactor operator has just completed withdrawing Bank D rods.* Step Counter SC CB-D1 reads 233 steps* Step Counter SC CB-02 reads 232 steps* ALR 00-82F "Bank D Full out Rod Stop" alarms* NPIS agrees with step counters* P/A converter indicates Bank D rods at 233 stepsSelect from the following the response which correctly describes the above conditions. A. System indications are consistent with anticipated plant conditions and operator response can proceed IAW ALR 00-82F.B. Group 1 rods are at 231 steps actual and Groups 2 rods are at 230 steps actual as Group 1 always leads Group 2.C. C-11 has malfunctioned and should have prevented demand from exceeding 232 steps on Group 1 rods.D. Control Bank D Group Step Counter SC CB-02 is reading incorrectly and must always agree with the P/A converter.

Back 74

A