AOP-3 Flashcards by Danny W

Given the following conditions:

• The plant is in MODE 3 at normal operating temperature and pressure.
• Charging and letdown have been maximized for PCS chemistrJ.
• Over the last several hours, Source Range Nls Count Rate has risen slightly. Which of the following may be the cause of the change in Source Range Count Rate?
A. Letdown Temperature Controller TIC-0203 setpoint has been lowered from 110°F to 90°F.

B. Letdown Temperature Controller TIC-0203 setpoint has been raised from 110°F to 120°F.

C. VCT hydrogen pressure has been raised from 20 psig to 30 psig.
D. VCT hydrogen pressure has been lowered from 30 psig to 20 psig.

A. Letdown Temperature Controller TIC-0203 setpoint has been lowered from 110°F to 90°F.

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Which of the following is NOT a symptom of ONP-11.1, Fuel Cladding Failure?

A. Containment High Radiation (CHR) signal

B. Stack Gas Monitor High radiation indication or alarm

C. PCS sample analysis indicates high activity

A. Containment High Radiation (CHR) signal

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Which of the following conditions is NOT an indication of a Loss of Condenser Vacuum?

A. Rising turbine backpressure B. Lowering turbine backpressure
C. Lowering condenser vacuum.

D. Mn Feed Pump Turbine seal pressure

B. Lowering turbine backpressure

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Which ONE of the following IS NOT a symptom of a Loss of Main Feedwater (ONP-3)?

A. Main Feedwater throttle and trip valves indicating “closed”.

B. “B” Condensate Pump trip alarms and green indicating light.

C. Main Feed suction pressure = 200 psia.

D. Closure of “A Main Feed Reg Valve and “A” S/G level at 85%.

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The plant is in MODe 6 with refueling operations in progress with P-67A in service.

Which of the following describes electrical buses that if lost, would require entry into Loss of shutdown cooling for the above plant conditions.
A. Inst AC Bus Y-01 or Bus 1C
B Pref AC bus Y-20 or Bus 1D
C. Pref AC bus Y-10 of Instr AC Bus Y-01
D. Inst AC Bus Y-01 or Bus 1D

B Pref AC bus Y-20 or Bus 1D

????????

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Which ONE of the following is an indication of an excessive feedwater event?
A. Reactor power rising.

B. Pressurizer pressure rising.

C. TAVE rising.

D. Steam Generator level lowering

A. Reactor power rising.

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Which ONE of the following is an indication of an excessive feedwater event?

A. Main Feed Pumps recirc CVs opening.

B. Pressurizer pressure rising.

C. TAVE rising.

D. TAVE lowering.

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Given the following conditions:

Self-Study

The plant is operating at 95% power when power rises 3% in one minute.
Power then levels off.
Audible steam flow to the atmosphere is noted.

Which ONE of the following is an additional symptom of this event?

A. Pressurizer level rising.
B. Pressurizer pressure lowering.
C. PCS Tave rising.
D. Indicated Nl power lowering

B. Pressurizer pressure lowering

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Given the following conditions:
.. The plant was operating at 21% power when a loss of load occurred.
.. Reactor power is now 13%.
.. The cause of the loss of load was a turbine governor valve control malfunction. Which ONE of the following will be an indication of this failure?
A. Pressurizer pressure raising.

B. Pressurizer pressure lowering.

C. Pressurizer level lowering.
D. No change in pressurizer level or pressure.

A. Pressurizer pressure raising.

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Given the following conditions:
• The plant is operating at 100% power.
• The operator observes that reactor power is rising and Loop 1 and 2 TAvE/T REF gross deviation alarm is in.

What other symptom should the operator observe to confirm that an uncontrolled Primary Coolant System dilution is taking place?

A. Pressurizer pressure rising.

B. Steam flow rate rising.

C. Steam generator pressure lowering.

D VCT level rising.

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Given the following plant conditions:

Ell Plant is in MODE 1 at 50% power
Ell No equipment is out of service

If a loss of load event were to occur, which ONE of the following symptoms will be evident?

A. TAVE lowering
B. Pressurizer pressure lowering C. Pressurizer level rising
D. DEH turbine load rising

C. Pressurizer level rising

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Given the following plant conditions: Plant is in MODE 1 at 50% power No equipment is out of service

If an excessive load event were to occur, which of the following symptoms will be evident?

A. Tave rising

B. Pressurizer pressure lowering

C. Pressurizer level rising

D. DEH turbine load lowering

B. Pressurizer pressure lowering

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Given the following plant conditions:
Plant is in MODE 1 at 100% power No equipment is out of service
An uncontrolled PCS boron dilution event occurs due to lowering Letdown temperature

Which of the following will NOT be a symptom of this event?

A. Reactor power rising

B. Tave rising

C. Tave/ Tref Gross Deviation Alarm

D. VCT level lowering

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Given the following plant conditions: Plant is in MODE 1 at 50% power No equipment is out of service
‘B’ channel PZR level and pressure control channels are in service Auxiliary Feedwater Pump P-8C in service for surveillance testing

Which of the following is a key symptom for a loss of Preferred AC Bus Y-10?
A. Lowering Main Feedwater Pump suction pressure

B. Pressurizer Spray Valves close

C. AFW Pump P-8C trips

D. Maximum Charging and minimum Letdown

A. Lowering Main Feedwater Pump suction pressure

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Given the following plant conditions:
Plant is in MODE 1 at 100% power
No equipment is out of service
‘A’ channel PZR level and pressure control channels are in service

Which of the following is a key symptom for a loss of Preferred AC Bus Y-20?

A. Lowering Main Feedwater Pump suction pressure

B. Pressurizer Spray Valves close

C. Channei’C’ RPS Trip Logic lights (all three rows)- ON

D. Maximum Charging and minimum Letdown

A. Lowering Main Feedwater Pump suction pressure

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Given the following plant conditions:
Plant is in MODE 1 at 100% power No equipment is out of service
‘A’ channel PZR level and pressure control channels are in service Which of the following is a key symptom for a loss of Preferred AC Bus Y-30?
A. Lowering Main Feedwater Pump suction pressure

B. Pressurizer Spray Valves close

C. Channel’C’ RPS Trip Logic lights (all three rows)- ON

D. Maximum Charging and minimum Letdown

C. Channel’C’ RPS Trip Logic lights (all three rows)- ON

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Given the following plant conditions:
Plant is in MODE 1 at 100% power No equipment is out of service
‘A’ channel PZR level and pressure control channels are in service Which of the following is a key symptom for a loss of Preferred AC Bus Y-40?
A. Lowering Main Feedwater Pump suction pressur

B. Pressurizer Spray Valves closes

C. Half Channel trip on CRD Clutch Power Supply

D. Maximum Charging and minimum Letdown

C. Half Channel trip on CRD Clutch Power Supply

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Given the following plant conditions:

The plant is on shutdown cooling (SOC) in reduced inventory.
P-67A LPSI Pump is in service. P-67B is NOT running.
All SOC system controls are aligned normally.
A leak develops in the Primary Coolant System.
A moment of two later LPSI injection flow becomes erratic and the following valid alarm then annunciates: EK-1157, LO PRESS Sl PUMPS P-67A & P-67B TRIP

Which of the following describes any required operator actions for these conditions?

A. Closely monitor operating parameters of P-67B since it has auto started, and there are potential cavitation concerns.
B. Since the LPSI Pump STANDBY auto start feature is not used, the operator must manually start P-67B to maintain SOC flow.
C. Since the LPSI Pump STANDBY auto start feature is not used, the operator must report that a Loss of Shutdown Cooling event has occurred.
D. The operator should attempt only one restart of P-67A to prevent exceeding motor starting duty limitations and to avoid a loss of shutdown cooling.

C. Since the LPSI Pump STANDBY auto start feature is not used, the operator must report that a Loss of Shutdown Cooling event has occurred.

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Which of the following conditions is NOT an indication of a loss or potential loss of

Component Cooling Water?

A. Tube leak in the Letdown Heat Exchanger, E-58.

B. Component Cooling Surge Tank annunciating on low level

C. Automatic start of P-528, standby Component Cooling Water pump v

D. Primary Coolant pump P-50A Seal Heat Exchanger high temperature

A. Tube leak in the Letdown Heat Exchanger, E-58.

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Given the following conditions:

• The plant is at 100% power.
• A failure of the Low Pressure Letdown Temperature Controller, TIC-0203, has resulted in the actual Letdown temperature dropping 10 degrees from setpoint
(e.g. from 11ooF to 100°F).

Which of the following describes the expected response of plant parameters due to this event? Assume no.operatoraction has.been.taken.

A. TAvE rises; Reactor power rises initially and then returns to near original value.

B. TAvE does not change; Volume Control Tank level rises.

C. Pressurizer level remains steady; Reactor power lowers.

D. Volume Control Tank level rises; TAVE lowers.

A. TAvE rises; Reactor power rises initially and then returns to near orA. TAvE rises; Reactor power rises initially and then returns to near original value.iginal value

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Match the expected observable trend for the following parameters during a small S/G tube leak (

A. 3
B. 3
C. 3
D. 1
E. 2

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With the plant at 10% power, RIA-1805, Containment Area Radiation Monitor, suffers a short causing it to fail high. While investigating this issue Preferred AC Bus Y-30
de-energizes. What effect does this have on the plant?

A. A reactor trip due to closure of the MSIV’s

B. A turbine trip due to closure of the MSIV’s

C. Loss of Instrument Air to the Pressurizer Spray Valves
D. PCP controlled bleed-off being controlled by a relief valve

D. PCP controlled bleed-off being controlled by a relief valve
D) Correct- This will result in a loss/trip of 2 of 4 Containment Area Radiation Monitors (loss of Y-30 results in loss of power to RIA-1807) which will cause a containment isolation on high radiation (CHR). The MSIV’s will not close.

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Given the following plant conditions:
Plant is in MODE 1 at 100% power No equipment is out of service
An uncontrolled PCS dilution event occurs Assume no operator actions are taken

Which of the following describes the effect on key symptoms?

A. Reactor power rises and stabilizes at higher value
B. VCT level rises
C. Tave lowers
D. Tave rises initially, then lowers to pre-event value

B. VCT level rises

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Given the following plant conditions:

Plant is in MODE 1 at 100% power
No equipment is out of service
A loss of load event occurs due to partial closure of one Main Turbine Governor Valve
Assume no operator actions are taken

Which of the following describes the effect on key symptoms?
A. Reactor power lowers and stabilizes at lower value
B. Pressurizer pressure lowers
C. TAVE lowers
D. TAVE rises initially, then lowers to pre-event value

A. Reactor power lowers and stabilizes at lower value

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Given the following plant conditions: Plant is in MODE 1 at 100% power No equipment is out of service An excessive load event occurs due to small steam leak in the Turbine Building Assume no operator actions are taken Which of the following describes the effect on key symptoms? A. Reactor power rises and stabilizes at higher value B. Pressurizer pressure rises C. Tave rises D. Tave lowers initially, then rises to pre-event value

A. Reactor power rises and stabilizes at higher value

Given the following conditions: Self-Study o A trip of a Main Feed Pump occurred at 75% power • Power is being reduced rapidly • The current conditions are as follows: • "A" Steam Generator level is 36% and just starting to trend upward • "B" Steam Generator level is 34% and just starting to trend upward • "A" Steam Generator feed flow is 3.4 E6 lbm/hr o "B" Steam Generator feed flow is 3.4 E6 lbm/hr • "A" Steam Generator steam flow is 3.3 E6 lbm/hr • "B" Steam Generator steam flow is 3.3 E6 lbm/hr What is the appropriate course of action for these conditions? A. Trip the reactor since this should have already occurred automatically B. Stop the power reduction and stabilize steam generator levels to avoid excessive positive reactivity C. Stop the power reduction and return S/G levels slowly to programmed level to avoid excessive positive reactivity D. Continue the power reduction until steam generators are back to program level to avoid a low S/G level trip

C Stop the power reduction and return S/G levels slowly to programmed level to avoid excC. Stop the power reduction and return S/G levels slowly to programmed level to avoid excessive positive reactivityessive positive reactivity

Operators are reducing power rapidly due to a trip of Cooling Tower Pump P-398. The Shift Engineer notes that rods have been inserted below the Power Dependent Insertion Limit (POlL) for the current power. What is the appropriate action? A. Trip the reactor since the required shutdown margin has been violated B. Commence a rapid boration since the required shutdown margin has been violated C. Stop the power reduction until rods are above POlL since voluntary entry into LCO Condition 3.1.6.A is not allowed D. Continue the power reduction and raise rods above the POlL limit as necessary upon completion of the power reduction

D. Continue the power reduction and raise rods above the POlL limit as necessary upon completion of the power reduction

A normal plant shutdown is in progress, and the following conditions exist: * Reactor power is 90% * The instrument air supply line to Main Feed Regulating Valve CV-0701 breaks upstream of the filter F-46 If the reactor were to trip under these conditions, this could result in: A. Overcooling of the PCS and a safety injection if MainFeed Pumps are not tripped or the Feed Block Valves are NOT closed. B. Lifting of the Pressurizer code safeties due to the large reduction in feedwater caused by the instrument line break C. Overcooling of the PCS and a safety injection since the atmospheric steam dump valves will fail open due to the instrument air line break D. Lifting of steam generator code safeties since the atmospheric dump valves will fail due to the instrument air line break

A. Overcooling of the PCS and a safety injection if MainFeed Pumps are not tripped or the Feed Block Valves are NOT closed

With the plant at 100% power Control Rod 35 (Group 3 rod very center of the core) drops halfway into the core (66 inches withdrawn). Five minutes after the rod has dropped into the core what will ASI be, how will the Nl power indications compare to the actual core power, and what action should be taken to lower core power? A. ASI will be positive, Nl power will be lower than actual, lower power with group 4 up to80inchesinserted B. ASI will be positive, Nl power will be higher than actual, borate to lower reactor power C. ASI will be negative, Nl power will be lower than actual, lower power with group 4 up BOinchesinserted D. ASI will be negative, Nl power will be higher than actual, borate to lower reactor power

B. ASI will be positive, Nl power will be higher than actual, borate to lower reactor power Power will be suppressed in the top of the core. In aCE plant that results in ASI being positive. Nl power will be higher than actual because the radial core power profile will have shifted toward the exterior. Xenon effects are minimized by the short time frame of the question (i.e. 5 minutes) Since the Nl's are primarily monitoring the exterior of the core they will be at an elevated power compared to actual core power until they are recalibrated. In ONP-5.1 rods are not to be used to lower core power. This reduces the value of the dropped rod and maintains the maximum shutdown margin.

Given the following plant conditions: - The reactor is operating at 72% power - Power escalation is in progress. - Main Feed pumps P-1A and P-1Bare in service The following alarm annunciates: EK-0143 FW Pump P-1A/Turbine K-7Atrip Which of the following describes the immediate actions required for the above conditions? A. Trip the reactor, enter EOP-1 actions. B. Take manual control of P-1B MFP controller and raise speed of P-1B, commence rapid power reduction. C. Take manual control of Feed water regulating valves and raise open signal, commence rapid power reduction. D. Take manual control of MFP combined speed controller and raise speed of P-1A and P-1B, commence rapid power reduction

B. Take manual control of P-1B MFP controller and raise speed of P-1B, commence rapid power reduction.

Given the following plant conditions: * Plant is in MODE 1 at 85% power. * At 0600 an Unusual Event was declared due to a seismic event. * At 1120 an aftershock is felt by control room and other plant personnel. The Control Room Supervisor directs the control room personnel to walk down the panels and note any abnormal parameters. Containment pressure is observed to be slowly lowering. Based on these symptoms what is the appropriate course of action? A. Commence emergency boration and trip the reactor. B. Commence a controlled plant shutdown by boration only and reduce Tave below 525F C. Reduce power to less than 15% and then inspect containment to determine extent of damage. D. Commence a controlled plant shutdown and place the Plant in Mode 5 per Technical Specification LCO 3.6.1 if the breach is not repairable

A. Commence emergency boration and trip the reactor.

The plant is operating at 75% power when the following plant conditions occur: * Steam Generator Level A- 65% and stable * Steam Generator Level B - 80% and rising * Steam Generator Pressure A - 740 psia and stable * Steam Generator Pressure B - 700 psia and lowering * Pressurizer Pressure - lowering * Pressurizer Level - lowering * TAVE - lowering * Containment parameters are stable The S/G high level override will actuate if "B" S/G level reaches approximately 85%. Predict the effect on the plant if the high level override fails to actuate? A. Main steam line components may be water hammered from water in the steam lines. B. Moisture carryover to the turbine which could possibly result in turbine damage. C. Main Feed Pumps operating at runout conditions resulting in a MFP turbine trip. D. PCs will be overcooled resulting in tripping of the pressurizer heaters.

B. Moisture carryover to the turbine which could possibly result in turbine damage.

A loss of most of the Control Room alarm panels would usually require entry into which Off Normal Procedure? A. Loss of Preferred AC Buses Y-30 (ONP-24.3). B. Loss of Instrument AC Bus Y-01 (ONP-24.5). C. Loss of DC Power (ONP-2.3).' D. Loss of AC Power (ONP-2.1).

C. Loss of DC Power (ONP-2.3).'

The Plant is at 100% power. Self-Study Among numerous alarms, the following key alarms have just annunciated and are in solid: • EK-0504, "2400V BUS 1D BKR 152-203 TRIP" • EK-0522, "BUS FAIL TO TRANSFER" • EK-0556 "DIESEL GEN NO 1-2 FAIL TO START" • EK-0557, "DIESEL GEN NO 1..:2 TROUBLE" Right channel Safety Injection Loop Motor Operated Valves indicating lights on Panel C-03 are out (no red or green indications). Which Off Normal Procedure should be entered? A. Loss of Preferred AC Bus Y-20 (ONP-24.2). B. Loss of DC Power (ONP-2.3). C. Loss of Preferred AC Bus Y-40 (ONP-24.4). D. Loss of AC Power (ONP-2.1).

D. Loss of AC Power (ONP-2.1).

Given the following conditions: ( .. The Plant is at 100% power. Self-Study .. A lightning strike on-site has generated multiple spurious alarms. .. With no operator action, all alarming windows go dark, and, .. The Trip Power light is out for Main Feed Pump K-7B. Which Off Normal Procedure should be entered? A. Loss of Preferred AC Bus Y-20 (ONP-24.2). B. Loss of DC Power (ONP-2.3L C. Loss of Instrument AC Bus Y-01 (ONP-24.5). D. Loss of AC Power (ONP-2.1).

B. Loss of DC Power (ONP-2.3L

The plant is operating at full power when the following plant conditions occur: • Steam Generator Level A - 65% and stable • Steam Generator Level B- 78% and rising • Steam Generator Pressure A - 740 psia and stable • Steam Generator Pressure B - 710 psia and lowering • Pressurizer Pressure - lowering • Pressurizer Level - lowering • TAvE- lowering • Steam Generator A feed flow - 5.6 x 106 lbm/hr and stable • Steam Generator B feed flow- 5.85 x 106 lbm/hr and rising • Steam Generator A steam flow - 5.6 x 106 lbm/hr • Steam Generator B steam flow- 5.6 x 106 lbm/hr • Containment parameters are stable Based on the preceding plant parameters, which plant procedure would you use to correct the problem? A. ONP-9 (Excessive Load Increase). B. ONP-3 (Loss of Main Feedwater). C. ONP-10 (Excessive Feedwater Increase). D. SOP-12 (Main Feedwater).

C. ONP-10 (Excessive Feedwater Increase).

Given the following: Self-Study ``` • The Plant is operating at full power. • PCS pressure is slowly lowering • PZR level is slightly lowering • Tave is constant • Charging Flow is rising • Letdown Flow is constant • VCT level is lowering • Off-gas Monitor (RIA-0631) is slowly rising Which ONE of the following ONPs should be entered? A. ONP-9, Excess Load Increase. B. ONP-18, Pressurizer Pressure Control Malfunction. C. ONP-23.1, PCS Leak. D. ONP-23.2, Steam Generator Tube Leak. ```

D. ONP-23.2, Steam Generator Tube Leak.

Given the following plant conditions: Plant is in MODE 1 at 100% power Among numerous alarms, the following key alarms have just annunciated and are in solid: o EK-0503, "2400V BUS 1C BKR 152-105 TRIP" o EK-0522, "BUS FAIL TO TRANSFER" • EK-0550, "DIESEL GEN NO 1-1 FAIL TO START" • EK-0551, II DIESEL GEN NO 1-1 TROUBLE" Left channel Safety Injection Loop Motor.Operated Valve indicating lights on Panel C-03 are out (no red or green indications). Which Off Normal Procedure should be entered? A. Loss of Preferred AC Bus Y-10 (ONP-24.1) B. Loss of DC Power (ONP-2.3) C. Loss of Preferred AC Bus Y-30 (ONP-24.3) D. Loss of AC Power (ONP-2.1)

D. Loss of AC Power (ONP-2.1)

Given the following: • Reactor is at 100% power • Nl-06 indicates 0 • Loss of TMM Channel "B" Self-Study • Lowering main feedwater pump suction pressure • AFW flow control valves CV-0736A and CV-0737A have failed open Which event has occurred? A. Loss ofY-10. B. Loss of Y-20. C. Loss of Y-30. D. Loss of Y-40.

B. Loss of Y-20.

The plant is at 100% power when the following conditions are noted: • All Channel "A" RPS bistables indicate tripped • "A" TMM channel indicating screen is blank • Nl-05 indicates 0 (% power) • Charging flow is 133 gpm • Letdown flow is 40 gpm • Main feed pump P-1A recirc valve CV-0711 indicates open Which event has occurred? A. Loss of Y-40. B. Loss of Y-30. C. Loss of Y-20. D. Loss of Y-10

D. Loss of Y-10

The Plant was at 80% power steady state when the following occurred: Both Loop 1 and Loop 2 TAvE/T REF Gross Deviation alarms have annunciated a No other alarms have annunciated. a VCT level is stable. PZR level is rising and is currently at 58%. PZR pressure is rising and is currently at 2070 psia. Which (if any) Off Normal Procedure should be entered? A. Loss of Load (ONP-1). B. Uncontrolled Primary Coolant System Boron Dilution (ONP-8). C. Excessive Load (ONP-9). D. TAVEITREF Controller Failure (ONP-13).

A. Loss of Load (ONP-1).

The plant is at 100% power when the following indications are LOST: • Indications on Quench Tank Level, Pressure, and Temperature • Indications on Startup, Intermediate, and Power Range Recorders • Containment Temperature and Humidity indications • Wide Range Level and Pressure indications • Loss of Rod Matrix Lights • Letdown and Charging Temperature, and Flows indications • Boric Acid Tanks Level indications • VCT Level, Pressure, and Temperature indications • Position indication on Feedwater Reg. Valves • Temperature indications for Pressurizer PORV and Safety Discharge, Water, Vapor, Surge, and Spray Line • NUMEROUS ALARMS ARE RECEIVED What event is occurring? A. Loss of DC power. B. Loss of Instrument AC Bus (Y-01). C. Loss of Preferred AC Bus Y-10. D. Loss of Preferred AC Bus Y-20.

B. Loss of Instrument AC Bus (Y-01).

The plant is at 100% power when the following conditions are noted: • All Channel "D" RPS bistables indicate tripped • "D" TMM channel indicating screen is blank • Nl-08 indicates 0 (% power) Which event has occurred? A. Loss of Y-40 B. Loss of Y-30 C. Loss of Y-20 D. Loss of Y-10

A. Loss of Y-40

``` Given: • Reactor is at 100% power. • Nl-07 indicates 0. • Loss of TMM Channel "C". Which event has occurred? A. LossofY-10 ``` B. Loss of Y-20 C. Loss of Y-30 D. Loss of Y-40

C Loss of Y-30

With the plant at full power a loss of all offsite power occurs. DIG 1-1 FAILS to start ( automatically, or manually. Which one of the following describes an effect on the noted Component Cooling Water Pump, and what procedure will be used to address the concern? A. P-528 discharge pressure may be less than required. Per SOP-16, Component Cooling Water System, stop P-528 if CCW heat exchanger deltaP limits are exceeded. B. P-52A discharge pressure may be less than required. Per ONP-6.2, Loss of CCW, start all available CCW pumps. C. P-52B discharge pressure may be less than required. Per ONP-2.1, Loss of AC Power, isolate selected radwaste loads if needed to restore discharge pressure. D. P-52C discharge pressure may be less than required. Per SOP-16, Component Cooling Water System, isolate selected radwaste loads to restore discharge pressure.

C. P-52B discharge pressure may be less than required. Per ONP-2.1, Loss of AC Power, isolate selected radwaste loads if needed to restore discharge pressure.

Given the following plant conditions: PCS temperature is 4200F. LTOP System is armed in LTOP Mode. Charging pump P-55A is in operation. Letdown is in service. 125 VDC Panel D11-1 has deenergized due to a fault. To address these conditions, the Control Room Supervisor.will ... A. direct the crew to reestablish Charging and Letdown flow per SOP-2A, "Chemical and Volume Control" since letdown flow automatically isolated due to loss of D-11-1. B. implement ONP-23.1, "Primary Coolant System Leak" since RV-2006 has lifted due / to closure of CV-2009 (Letdown Containment Isolation Valve), and will not reseat. C. direct the crew to bypass the CVCS purification demineralizers due to CV-0909, Letdown Hx CCW Outlet, failing CLOSED. D. implement ONP-23.1, "Primary Coolant System Leak" since a PORV has lifted due to loss of D-11-1.

B. implement ONP-23.1, "Primary Coolant System Leak" since RV-2006 has lifted due / to closure of CV-2009 (Letdown Containment Isolation Valve), and will not reseat. CORRECT - Loss of D-11-1 causes CV-2009 to close; however, letdown is still flowing from PCS into the letdown line upstream of CV-2009. In the flowpath is RV-2006 which will lift due to the higher letdown pressure.

Given the following conditions: - Steam Generator Nozzle Dams are installed. - Fuel is being moved from the core to the Spent Fuel Pool. - EK-1349 and EK-1350, Containment Sump Hi Hi Level, alarm annunciates. - Containment Radiation Monitors, RIA-2316 and RIA-2317, indicate rising radiation levels. Which of the following procedures has IMMEDIATE ACTIONS which must be performed for these conditions? A. ONP-11.1, Fuel Cladding Failure B. ONP-11.2, Fuel Handling Accident C. ONP-17, Loss of Shutdown Cooling D. ONP-23.3, Loss of Refueling Water Accident

D. ONP-23.3, Loss of Refueling Water Accident

Refueling operations are in progress when the following alarm annunciates: EK-1364, GASEOUS WASTE MONITORING HI RADIATION The alarm is due to a valid high alarm condition on RIA-5712, Fuel Handling Area Vent monitor. In response to this condition, the Control Room Supervisor will use ... A. SOP-24, "Ventila.tion and Air Conditioning Systems", to direct a manual shutdown of the Fuel Handling Area ventilation system. B. ONP-11.2, "Fuel Handling Accident" which will direct verification of the automatic tripping of V-69 Supply Fan, and to direct certain manual actions. C. SOP-38, "Gaseous Process Monitoring System" which will direct verification of the automatic tripping of V-70A and V-708 Exhaust Fans. D. SOP-24, "Ventilation and Air Conditioning Systems" which will direct verification of the automatic tripping of only ONE of the V-70 Exhaust Fans.

B. ONP-11.2, "Fuel Handling Accident" which will direct verification of the automatic tripping of V-69 Supply Fan, and to direct certain manual actions

The Plant was at 100% power steady state when the following occurred: ( Loop 1 and Loop 2 TAVE/TREF Gross Deviation alarms have annunciated Reactor power is lowering. DEH turbine load is constant. Which Off Normal Procedure should be entered? A. Loss of Load (ONP-1). B. Control Rod Drop (ONP 5.1) C. Uncontrolled Primary Coolant System Boron Dilution (ONP-8). D. TAVE/TREF Controller Failure (ONP-13).

B. Control Rod Drop (ONP 5.1)

Among numerous alarms, the following key alarms have just annunciated and are in solid: EK-0504, "2400V BUS 1D BKR 152-203 TRIP" EK-0522, "BUS FAIL TO TRANSFER" EK-0556 "DIESEL GEN NO 1-2 FAIL TO START" EK-0557, "DIESEL GEN NO 1-2 TROUBLE" Right channel Safety Injection Loop Motor Operated Valves indicating lights on Panel C-03 are out (no red or green indications). Which Off Normal Procedure should be entered? A. Loss of Preferred AC Bus Y-20 (ONP-24.2). B. Loss of DC Power (ONP-2.3). C. Loss of Preferred AC Bus Y-40 (ONP-24.4). D. Loss of AC Power (ONP-2.1).

D. Loss of AC Power (ONP-2.1)

The plant is at 100% power. The following abnormal conditions exist: ( • Loop 1(2) TAVEITREF Gross Deviations alarms have annunciated. • Pressurizer Pressure is lowering from 2060 towards 2000 psia. • P-55A Charging Pump speed is rising. • DEH Turbine Load is rising above 100% power. Which ONP should be entered? A. ONP-13, TAVEITREF Controller Failure B. ONP-9, Excessive Load C. ONP-8, Uncontrolled Primary Coolant System boron Dilution D. ONP-1, Loss of Load

B. ONP-9, Excessive Load

• The Plant is at 100% power. Self-Study • No equipment is out of service. The NCOR notes Instrument Air alarms initiating. Instrument Air pressure drops initially to approximately 80 psig and is now cycling between 80 psig and 90 psig every 5 minutes. The NCOR notes that alarm EK-1111, "INSTRUMENT AIR DRYER TROUBLE", alarm IS NOT annunciated. Choose the correct statement concerning the status of the Instrument Air System. (Assume no Operator action.) A. All three lnstrumentAir Compressors are running (C.,2A, C-2B, C-2C). B. Feedwater Purity Air cross-connect (CV-1221) has failed open. C. Only Instrument Air Compressors C-2A and C-2C are running. D. Service Air Header Isolation CV-1212 has failed open.

A. All three lnstrumentAir Compressors are running (C.,2A, C-2B, C-2C). ????????

Plant power level is 100%. Which of the following AUTOMATIC Actions are expected to occur due to a loss of 2400 volt AC Bus 1D? A. BOTH 0/Gs start. B. Only 1-2 DIG starts. C. Neither D/G starts. D. Only 1-1 D/G starts.

B. Only 1-2 DIG starts.

Plant conditions: • Reactor Power = 100% Self-Study * "A" S/G level= 75% and rising. * "B" S/G level = 65% and rising slowly. * The S/G Water Level Control System is in full automatic lAW SOP-12 Choose the correct statement. A. The "A" S/G High Level Override function will cause the "A" S/G Main Feed Reg Valve to close at approximately 85% S/G level. B. If the "A" S/G High Level Override function operates per design, S/G levels should v not rise above 75%. C. If the "A" S/G level is due to a failure of the S/G Water Level Controller (LIC-0701 ), v the ONLY method of preventing S/G level from reaching 100% is by manual control. D. If "A" S/G level rises to 95%, an automatic reactor trip will occur."

A. The "A" S/G High Level Override function will cause the "A" S/G Main Feed Reg Valve to close at approximately 85% S/G level.

Given the following plant conditions: .. Reactor Power = 100% .. "A" S/G level = 88% "' "B" S/G level = 64% .. The Steam Generator Water Level Control System is in automatic lAW SOP-12 .. No Automatic Actions have occurred .. The NCO has taken manual control of the "A" S/G Level Indicating Controller Choose the correct statement below: A. Manual control of the "A" S/G Level Indicating Controller defeats the High Level Override function. B. The "A" S/G High Level Override function should be closing the "A" S/G Main Feed Reg Valve. C. The "A" S/G High Level Override function should be closing the "A" S/G Main Feed Reg Valve and lowering the speed of "B" Main Feed Pump to 3250 rpm. D. The "A" S/G level controller's High Level Override function will close the "A" S/G Main Feed Reg Valve if S/G level rises to 90%.

B. The "A" S/G High Level Override function should be closing the "A" S/G Main Feed Reg Valve.

Which ONE of the following is an automatic action of a Loss of Main Feedwater event (ONP-3)? A. Condensate pump trip. Y B. S/G high level override activation. Y C. AFAS initiation. D. S/G water level controllers swap to MANUAL mode.

C. AFAS initiation.

Which ONE of the following is an automatic action due to a Loss of Main Feedwater event (ONP-3)? A. S/G high level override activation. B. Condensate pump trip. C. Feed pump combined speed controller transferred to AUTO. D. Heater Drain Pump Discharge Throttle Valve (CV-0608) fully opens on low feed pump suction pressure

D. Heater Drain Pump Discharge Throttle Valve (CV-0608) fully opens on low feed pump suction pressure

Which ONE of the following is the MAXIMUM Condenser vacuum reading at which you would expect the Main Turbine to automatically trip? A. 25" Hg. B. 24" Hg. C. 21" Hg. D. 18" Hg

C. 21" Hg.

Given the following plant conditions: Plant is in MODE 1 at 100% power Alarm EK-0111, "Vacuum Low" has just alarmed Which of the following will result in an automatic reactor trip? A. Condenser vacuum reaches 24" Hg B. Condenser vacuum reaches 21.5" Hg C. Condenser vacuum reaches 18" Hg D. Both Cooling Tower Pumps trip

C. Condenser vacuum reaches 18" Hg

Given the following plant conditions: * Plant is in MODE 1 at 90% power * No equipment is out of service * P-8A, Auxiliary Feedwater Pump is operating for surveillance testing * DC Bus D-20R de-energizes Which of the following automatic actions will occur? A. Reactor trip B. P-8B, Steam Driven Auxiliary Feedwater Pump starts C. P-8A, Auxiliary Feedwater Pump trips D. Main Feedwater control for the 'B' S/G shifts to Y-40 power

D. Main Feedwater control for the 'B' S/G shifts to Y-40 power

Given the following plant conditions: * Plant is in MODE 1 at 100% power * No equipment is out of service * Both operating Service Water Pumps trip Which ONE of the following automatic actions will occur? A. Reactor trip B. CV-1359, Noncritical Service Water Isolation Valve closes C. Standby Service Water Pump starts D. P-4, Screen Wash Pump trips

C. Standby Service Water Pump starts

ONP-12, "Acts of Nature" warns about potential consequences of having the Turbine Building Sump Pumps P-45A and B running continuously. What is the concern related to the continuous operation of P-45A and B? A. The high flow rates will allow oil to make it out to the lake. B. The supply breakers are not sized for continuous operation. C. Prevents transfer from the Feedwater Purity.Building.sumps, which may overflow. D. May cause water to be transferred into the Dirty Waste Drain Tank T-60A/B

D. May cause water to be transferred into the Dirty Waste Drain Tank T-60A/B

Given the following plant conditions: ( • Plant is in MODE 5 with the PCS depressurized and vented • No equipment is out of service • A loss of Instrument AC Bus Y-01 occurs Which ONE of the following automatic actions will occur? A. Operating LPSI Pump trips B. Safety Injection initiates C. Charging Pump Suction shifts to the SIRWT D. Main Feed Pumps slow to minimum speed

C. Charging Pump Suction shifts to the SIRWT •

``` Given the following plant conditions: Plant is in MODE 3 at 530°F P-8C, Auxiliary Feedwater Pump is operating No equipment is out of service A loss of Instrument AC Bus Y-01 occurs ``` Which of the following automatic actions will occur? A. P-8C, Auxiliary Feedwater Pump trips B. P-8B, Steam Driven Auxiliary Feedwater Pump starts C. CRHVAC shifts to emergency mode D. Maximum Charging flow, zero Letdown flow

D. Maximum Charging flow, zero Letdown flow

Given the following plant conditions: ( Plant is in MODE 1 at 90% power P-8C, Auxiliary Feedwater Pump is operating for a surveillance test No equipment is out of service A loss of Instrument AC Bus Y-01 occurs Which of the following automatic actions will occur? A. Charging Pump suction shifts to the SIRWT B. P-8B, Steam Driven Auxiliary Feedwater Pump starts\ C. P-8C, Auxiliary Feedwater Pump trips D. Main Feedwater control for the 'A' S/G transfers to Y-30 power'1

A. Charging Pump suction shifts to the SIRWT

Given the following plant conditions: • Plant has just completed a refueling outage • Plant has just entered MODE 3 with 2 PCPs operating • No equipment is out of service • A spurious containment isolation occurs due to a CHP signal Which ONE of the following automatic actions will occur? A. Reactor trip B. Safety Injection initiates C. AFAS initiated D. MSIVs close

B. Safety Injection initiates

Given the following plant conditions: * The plant is in MODE 5 on Shutdown Cooling * No equipment is out of service * A spurious containment isolation occurs due to a CHP signal * All GOP actions have been taken Which ONE of the following automatic actions will occur? A. Operating LPSI Pump will trip B. Safety Injection initiates C. CRHVAC shifts to emergency mode D. Containment Spray initiates

C. CRHVAC shifts to emergency mode

Given the following plant conditions: Plant is in MODE 1 at 100% power No equipment is out of service A spurious containment isolation occurs due to a CHR signal Which of the following automatic actions will occur? A. Reactor trip B. Safety Injection initiates C. CRHVAC shifts to emergency mode D. MSIVs close

C. CRHVAC shifts to emergency mode

Given the following plant conditions: * Plant is in MODE 2 with reactor at 4% power * No equipment is out of service * A loss of Preferred AC Bus Y-30 occurs Which ONE of the following automatic actions will occur? A. Reactor trip B. Safety Injection initiates C. CRHVAC shifts to emergency mode D. Main Feedwater control for the 'A' S/G transfers to Y-10 power

A. Reactor trip

Given the following plant conditions: Plant is in MODE 2 with reactor at 2% power No equipment is out of service A loss of Preferred AC Bus Y-40 occurs Which of the following automatic actions will occur? A. Reactor trip B. Safetylnjection initiates C. CRHVAC shifts to emergency mode D. Main Feedwater control for the 'B' S/G transfers to Y-20 power

A. Reactor trip

Given the following plant conditions: Plant is in MODE 2 with reactor at 4% power No equipment is out of service A loss of Preferred AC Bus Y-20 occurs Which of the following automatic actions will occur? A. Reactor trip B. Safety Injection initiates C. CRHVAC shifts to emergency mode D. Main Feedwater control for the 'B' S/G transfers to Y-40 power

D. Main Feedwater control for the 'B' S/G transfers to Y-40 power

Given the following plant conditions: Plant is in MODE 2 with reactor at 4% power No equipment is out of service A loss of Preferred AC Bus Y-10 occurs Which of the following automatic actions will occur? A. Reactor trip B. Safety Injection initiates C. CRHVAC shifts to emergency mode D. Main Feedwater control for the 'A' S/G transfers to Y-30 power

D. Main Feedwater control for the 'A' S/G transfers to Y-30 power

Given the following conditions: * The plant has experienced a loss of all 2400 VAC power. * The reactor tripped. * Both D/Gs started and loaded as expected. * A Safety Injection actuation has NOT occurred. Assuming all equipment operates as expected, and NO operator actions are taken, which of the following is the expected state of Service Water Pump P-7C and CV-1359, Non-Crit. Service Water Isolation at 15 minutes after the loss of all 2400 VAC power initiated? A. CV-1359 OPEN, P-7C running. B. CV-1359 OPEN, P-7C stopped. C. CV-1359 CLOSED, P-7C running. D. CV-1359 CLOSED, P-7C stopped.

C. CV-1359 CLOSED, P-7C running.

The plant is at full power when a spurious Containment High Pressure isolation occurs. The reactor will automatically trip on ... A. Low steam generator level. B. High PCS pressure. C. Thermal Margin/Low Pressure. D. Loss of Load.

D. Loss of Load.

Given the following plant conditions: * The plant is at full power. * A loss of Bus 1D has occurred. * The crew is implementing ONP-2.1, "Loss of AC Power" and ONP-6.1, "Loss Service Water". * D/G 1-2 automatically started and loaded per design. * Service Water critical header pressures are 75 psig and stable. * 1 hour later the Jacket Water Temperature for D/G 1-2 as read on Tl-1492 indicates 175 degrees F and is slowly rising. Which one of the following actions is appropriate for the above conditions? A. Start an additional Service Water Pump. B. Trip D/G 1-2 immediately from the Control Room. C. Trip D/G 1-2 using the Overspeed Trip Lever. D. Ensure an Auxiliary Operator continues to monitor Jacket Water temperature.

D. Ensure an Auxiliary Operator continues to monitor Jacket Water temperature.

During the performance of ONP-20, "Diesel Generator Manual Control" what is the effect of placing DIG 1-1 Remote Local Transfer Switch (RLTS) to the LOCAL position? A. 125VDC Panel D-11A isolates from Station Battery #1. B. DIG 1-1 will immediately start and load. C. D/G 1-1 cannot be started or stopped from the Control Room D. The mechanical governor is disabled.

C. D/G 1-1 cannot be started or stopped from the Control Room

Which ONE of the following is an automatic action associated with ONP-10, Excessive Feedwater Increase? A. Main Feedwater System control shifts to Manual. B. Reactor trip if S/G level greater than 90% and reactor power is greater than 15%. C. Turbine trip if S/G level greater than 140% and reactor power is less than 15%. D. Main Feed Reg. Valve high level override actuates at 84.7%.

D. Main Feed Reg. Valve high level override actuates at 84.7%.

Which of the following valves will CLOSE on a Containment High Pressure signal, but will remain OPEN on a Containment High Radiation signal? A. CV-2083, Controlled Bleed-off Containment lsol valve. B. CV-0770, SG 'B' Bottom Slowdown valve. C. CV-0701, SG 'A' Main Feed Reg Valve. D. SV-2414A, Hydrogen Monitor Right Channel solenoid valve.

C. CV-0701, SG 'A' Main Feed Reg Valve.

Containment isolation has initiated due to Containment High Radiation. Both channels ( have actuated. During completion of EOP Supplement 6, Checksheet For Containment Isolation And CCW Restoration, all of the following containment isolation valves should be closed EXCEPT: A. CWRTs Vent CV-1064. B. CCW to Containment CV-0910. C. Controlled Bleedoff Containment Isolation CV-2083. D. S/G 'B' Bottom Slowdown CV-0770

B. CCW to Containment CV-0910.

A. Shield Cooling Surge Tank fill (CV-0939). B. CCW containment isolation (CV-091O)JC C. Main steam isolation valve (CV-0501 D. Main feedwater regulating valve (CV-0701

A. Shield Cooling Surge Tank fill (CV-0939).

``` Given: ( • RIA-1805 is at 8RIHR • RIA-1806 is at 15RIHR • RIA-1807 is at 12PJHR • RIA-1808 is at 9RIHR ``` Self-Study * Containment pressure is currently at 1.5 psig. (This is the highest containment pressure recorded.) * All automatic actions occurred. All of the following containment isolation valves should be closed EXCEPT: A. CWRTs Vent CV-1064. B. CCW to Containment CV-0910. C. Controlled Bleedoff Containment Isolation CV-2083. D. S/G 'B' Bottom Slowdown CV-0770.

B. CCW to Containment CV-0910.

Given the following plant conditions: * Plant is in Mode 1 at 100% power * Alarm EK-0111, "VACUUM LOW" has just alarmed due to air in-leakage. Assuming no operator actions, which ONE of the following describes the plant response if vacuum continues to lower? A. The turbine will trip when vacuum reaches 18" Hg B. The turbine will trip when vacuum reaches 22.5" Hg C. The turbine will trip when one of the bearings reaches 14 mils due to flow imbalance. D. RIA-0631, "Condenser Off Gas Flow Monitor'' counts will rise due to rising off gas flow.

A. The turbine will trip when vacuum reaches 18" Hg

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