Text

Initial Exam - 07/2002 - Draft Written Exam
	ML030630758
Person / Time
Site:	Callaway
Issue date:	08/23/2002
From:	Gody A; Operations Branch IV
To:	Randolph G; Union Electric Co
References
	50-483/02-301 50-483/02-301
	Download: ML030630758 (207)
	v • d • e

CALLAWAY PLANT EXAMINATION COVER SHEET TRAINING DEPARTMENT COURSE TITLE: RO INITIAL LICENSE EXAMINATION DATE:

NAME (Print): SCORING:

SIGNATURE: Points Possible: 100 Points Missed:

Grade:

DIRECTIONS: BLACK OUT CORRECT ANSWERS

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AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 1 An Electrician has called the Control Room requesting that the RO stroke CLOSED EJ HV-8804A, RHR TRAIN 'A' TO CHARGING PUMP SUCT ISO, for MOVATS testing. A LOCAL CONTROL (LC) tag is hanging on the MCB Handswitch.

Which ONE of the following complies with APA-ZZ-00310, Workman's Protection Assurance and Caution Tagging?

A. Stroke EJ HV-8804A if the Electrician is signed on to the LC.

B. The RO must sign on to the LC in addition to the Electrician requesting the valve stroke.

C. The RO may stroke the valve after verifying the LC is on SS Hold.

D. The Electrician signed on to the LC must come to the Control Room to operate the handswitch.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 2 Which ONE of the following events is required to be recorded in the RO Narrative Log?

A. ESW system ESFAS alarm that is unexpected.

B. Security intrusion alarm on door number 22033.

C. Main Feedwater System chemical additions.

D. Unscheduled placement of simulator halon to inhibit.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 3 During normal operation, GERE92, Condenser Air Removal Rad Monitor alarms. A steam generator tube leak is suspected. Given the following information:

Charging Flow: 120 gpm

Letdown Flow: 75 gpm

Pressurizer Level: 57% and STABLE

Tavg: 584.4°F and STABLE

RCP Seal Injection Flow: 8 gpm per pump

RCP Seal Leakoff Flow: 3 gpm per pump Which ONE of the following is the approximate steam generator tube leakage rate?

A. 25 gpm B. 33 gpm C. 37 gpm D. 45 gpm

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 4 The following plant conditions exist:

A Rx Startup is in progress following a mid-cycle outage

Rx power has been stabilized at 1E-8 amps

RCS temperature is at the no-load value

Critical data has been taken

Prior to any additional control rod movement, a single S/G Safety Valve on SG 'D' fails open and remains open

RCS Tavg decreases 9°F and reactor power starts to increase Which ONE of the following states the most restrictive action required to satisfy Technical Specification LCO(s)?

A. Reduce power range high flux reactor trip setpoints to < 85% rated thermal power.

B. Restore the inoperable S/G safety valve to operable status prior to entering Mode 1.

C. Restore Tavg or be in Mode 2 with Keff < 1.0 and all RCS TCold > 500°F within 30 min.

D. Immediately initiate emergency boration to restore adequate Shutdown Margin.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 5 The following plant conditions exist:

Mode 1, 100% power, all equipment in a normal full power lineup

4A Low Pressure Feedwater Heater level instrumentation indicates Hi Hi level.

Which ONE of the following describes the effect on MAIN FEEDWATER?

A. Temperature increases.

B. Flow increases.

C. Temperature decreases.

D. Flow decreases.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 6 FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, is in progress.

Which ONE of the following conditions is acceptable using Attachment 7, on the following page, for RCS Post-Soak Cooldown Limitations during recovery from the PTS condition?

A. RCS cold legs = 200°F. RCS wide range pressure = 0 psig.

B. RCS cold legs = 250°F. RCS wide range pressure = 300 psig.

C. RCS cold legs = 300°F. RCS wide range pressure = 400 psig.

D. RCS cold legs = 400°F. RCS wide range pressure = 300 psig.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 6 (continued)

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 7 A plant startup is in progress with power indicating 1E-8 amps on both channels of IR nuclear instruments.

Which ONE of the following will occur if IR channel N35 fails to 22%, current equivalent?

A. IR High Flux Reactor Trip.

B. IR Rod Stop will stop outward rod motion.

C. PR Low Flux Reactor Trip.

D. Pzr High Level Reactor Trip is unblocked.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 8 Which ONE of the following Core Exit Thermocouple (CETC) readings indicates the highest temperature during accident conditions at which a CETC will operate satisfactorily?

A. 700°F B. 1200°F C. 2300°F D. 3200°F

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 9 The following plant conditions exist:

Mode 1

Rx power 100%, normal operating temperature, normal operating pressure

NCP in service with BGFCV124 in auto

Letdown flow is 120 gpm

PZR level controller BBLK459 is in auto

BBLT461 is the upper select PZR level control channel BBLT461 fails HIGH. NO operator action is taken.

Which ONE of the following will occur as a result of BBLT461 failing?

A. The reactor will trip, but not as a result of PZR level.

B. After a time period, the reactor will trip on high PZR level.

C. After a time period, the reactor will trip on low PZR level.

D. The reactor will trip immediately on high PZR level.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 10 The plant is in Mode 2 at 3% Reactor Power, commencing warm-up of the main turbine.

Which ONE of the following could be a direct result of a loss of Vital AC Instrument Bus NN02?

A. Intermediate Range High Flux Reactor Trip.

B. Source Range High Flux Reactor Trip.

C. Charging Pump Suction Swaps to the RWST.

D. Idle Component Cooling Water Pump Start.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 11 The reactor tripped 5 minutes ago.

Which ONE of the following completes the statement concerning the heat transfer relationship between the RCS and Steam Generators?

The heat transfer rate between the RCS and the S/Gs will:

A. decrease as RCS temperature increases and AFW flow increases.

B. decrease as AFW temperature decreases and AFW flow increases.

C. increase as AFW temperature increases and RCS flow decreases.

D. increase as RCS temperature increases and AFW flow increases.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 12 Because of an administrative oversight OSP-NE-00001A, Standby Diesel Generator 'A' Periodic Tests (a Continuous Use Procedure) must be performed within the next 20 minutes to comply with the surveillance frequency requirements. The Secondary Equipment Operator reports that he CANNOT perform the Pre-Start Checks as required by the Initial Conditions in 20 minutes.

Which ONE of the following describes the action to be taken?

A. With SS permission, the diesel can be run without performing the Pre-Start Checks since it is always in standby and ready to start.

B. Generate a Temporary Change Notice for the Initial Conditions that removes the requirement for performing the Pre-Start Checks.

C. With SS permission, just perform selected portions of the Pre-Start checks so the diesel can be started within 20 minutes.

D. The Pre-Start Checks must be performed regardless of the time required to complete them.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 13 The following plant conditions exist:

Annunciator 80B, RPI NON-URGENT ALARM, is illuminated

DRPI General warning LED is flashing for rod H-8

There are NO rod control system alarms illuminated

DRPI indication for rod H-8 is 222 steps (Control Bank 'D', Group 2)

DRPI indications for remaining Control Bank 'D' rods are 216 steps.

Step counter indication for Control Bank 'D' Group 1 is 216 steps.

Step counter indication for Control Bank 'D' Group 2 is 215 steps.

Which ONE of the following has occurred in the rod position indication system?

A. Data 'A' failure B. Data 'B' failure C. Bank D, Group 1 step counter has failed D. Bank D, Group 2 step counter has failed

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 14 A Steam Generator Tube Rupture combined with a Loss of Offsite Power has occurred.

Which ONE of the following is the PREFERRED method to INITIALLY DEPRESSURIZE the RCS?

A. Cycle Pressurizer Heaters.

B. Use Auxiliary Spray.

C. Use Normal Pressurizer Spray.

D. Use a Pressurizer PORV.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 15 A large steam line break occurs inside containment. A Safety Injection occurs on Containment Pressure. Containment pressure is 30 psig when step 10 of Attachment 12 of E-0, "Check if CTMT Spray is Required", is performed.

Which ONE of the following is the reason for stopping all four RCP's?

A. They are an unnecessary addition of heat to Containment.

B. All RCP cooling water flow is automatically isolated.

C. Air is too dense for the motor cooler fans to keep the motor cool.

D. Containment structural failure is imminent.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 16 Which ONE of the following describes the plant response to a Hi Hi Radiation Alarm on GH RE-10B, Radwaste Building Exhaust Fans Discharge Header Radiation Monitor?

A. Radwaste Building Supply Unit (SGH01) STOPS.

B. Waste Gas Compressors (SHA02A & B) STOP.

C. Catalytic Hydrogen Recombiners (SHA01A & B) ISOLATE.

D. Gas Decay Tanks to RW HVAC Discharge Valve (HA HCV-14) ISOLATES.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 17 Which ONE of the following combinations of Borated Water Volume, Boron Concentration, and Solution Temperature would meet the Technical Specification LCO for the RWST in Mode 4?

Borated Water Volume Boron Concentration Solution Temperature A. 395,000 gal 2325 ppm 65°F B. 350,000 gal 2385 ppm 85°F C. 400,000 gal 2415 ppm 95°F D. 412,000 gal 2450 ppm 105°F

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 18 A seal water malfunction on the running condenser vacuum pump results in a degrading main condenser vacuum.

Which ONE of the following is the setpoint at which the standby condenser vacuum pump will automatically start?

A. 5.0 inches Hga B. 5.5 inches Hga C. 6.0 inches Hga D. 6.5 inches Hga

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 19 The following plant conditions exist:

Mode 1, 100% Reactor Power

RCS specific activity is 50 microcuries/gm DOSE EQUIVALENT I-131 Which ONE of the following is the Chemistry sampling requirements per OTO-BB-00005, Reactor Coolant System High Activity?

A. Normal 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sample requirements are necessary.

B. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until activity decreases for 3 consecutive samples.

C. As directed by the On-Shift Chemistry Supervisor.

D. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months until activity decreases to less than 1 microcurie/gm.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 20 Callaway Plant is in Mode 3 cooling down for a Refueling outage. The Reactor Operator has been directed to decrease RCS pressure to 1950 psig.

Which ONE of the following would the Reactor Operator have to set the Pressurizer Pressure Master Control, BBPK455A, to maintain the RCS at 1950 psig in Auto?

(Narrow Range Pzr Pressure range is from 1700 to 2500 psig.)

A. 1.77 turns B. 2.55 turns C. 3.13 turns D. 4.41 turns

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 21 An accessible area where an individual could receive a dose equivalent greater than

________________ in one hour at a distance 12 inches from the radiation source is classified as a ____________________.

A. 1000 mrem; CAUTION HIGH RADIATION AREA B. 100 mrem; RADIATION AREA C. 100 mrem; HOT SPOT D. 1000 mrem; DANGER HIGH RADIATION AREA

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 22 The following plant conditions exist:

Mode 1, 80% reactor power, 975 MWe

'A' and 'C' Circ Water pumps in operation

Ambient Dry Bulb temperature is -5°F, Cooling Tower Basin temperature is 45°F Utilizing Attachment 1 of OTN-DA-00001 on the following page, which ONE of the following is the correct status of the cooling tower?

A. Two bypass valves will open with two circ water pumps running.

B. All water flow is directed to the center of the cooling tower.

C. Three bypass valves will open with two circ water pumps running.

D. All water flow is directed to the outer portion of the cooling tower.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 22 (continued)

Attachment 1

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 23 A reactor startup is in progress. Power level is at 1E-7 amps when a reactor trip occurs due to a Nuclear Instrumentation Channel failure.

Which ONE of the following is the approximate length of time before the Source Range NIs will automatically energize?

A. 2 minutes B. 5 minutes C. 10 minutes D. 15 minutes

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 24 Which ONE of the following correctly identifies the parameters and values used by an operator to ensure the temperature difference between the PZR and the Spray Fluid are within the specified limit(s) in the Technical Specifications when initiating PZR Spray?

Spray Source T Limit Parameters Monitored To Satisfy T Limit Normal Spray 275°F RCS hot leg loop temperature and PZR vapor space temperature.

A. Aux Spray 583°F Regen HX charging inlet temperature and PZR vapor space temperature.

B. Normal Spray 275°F RCS cold leg loop temperature and PZR vapor space temperature.

Aux Spray 320°F Regen HX charging outlet temperature and PZR vapor space temperature.

C. Normal Spray 320°F RCS hot leg loop temperature and PZR vapor space temperature.

Aux Spray 583°F Regen HX charging inlet temperature and PZR vapor space temperature.

D. Normal Spray 320°F RCS cold leg loop temperature and PZR vapor space temperature.

Aux Spray 320°F Regen HX charging outlet temperature and PZR vapor space temperature.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 25 Per ODP-ZZ-00025, Emergency Operating Procedure Usage, in which ONE of the following cases may AFW be THROTTLED to less than 300,000 lbm/hr?

S/G NR Level Ctmt Temp Ctmt Rad A. A-30% C-24% 210°F 1 R/hr B-29% D-33%

B. A-3% C-17% 125°F 10 R/hr B-2% D-6%

C. A-17% C-18% 115°F 1 x 106 R/hr B-14% D-21%

D. A-16% C-0% 180°F 1 x 105 R/hr B-13% D-6%

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 26 The following plant conditions exist:

PZR Relief Tank Level Hi/Lo ALARMING on HIGH LEVEL

PZR Relief Tank Pressure ALARMING on HIGH PRESSURE Which ONE of the following combinations contain sources, ALL of which should be monitored for leakage into the PRT?

A. RHR Pump Suction Reliefs (EJ8708A/B), RCP Seal Leakoff Relief (BG8121), and CVCS Letdown Relief (BG8117)

B. ECCS Accumulator Reliefs (EJ8855A-D), RHR Pump Suction Relief (EJ8708A/B), and CVCS Letdown Relief (BG8117).

C. RCP Seal Leakoff Relief (BG8121), CVCS Letdown Relief (BG8117) and RHR Discharge Reliefs (EJ8856A/B)

D. Safety Injection Pump Suction Reliefs (EM8858A), RHR Pump Suction Reliefs (EJ8708A/B), and RCP Seal Leakoff Relief (BG8121).

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 27 Which ONE of the following could indicate a 10 gpm letdown leak between BGHV8152, CVCS Letdown System Outer CTMT Iso Valve, and the containment penetration?

A. BGPCV0131, CVCS Letdown Hx Outlet PCV, CLOSING to maintain pressure at setpoint.

B. INCREASED Component Cooling Water flow to the Letdown Heat Exchanger.

C. BGFI0132, CVCS Letdown Hx Outlet Flow Indicator, INCREASING.

D. BGTI0126, Regen Hx Charging Outlet Temperature Indicator, DECREASING.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 28 The following plant conditions exist:

Safety Injection actuated on Low Pzr Pressure and has NOT been RESET.

CTMT pressure is 10 psig and increasing at 1 psig/minute.

NB01 is energized from off-site power.

NB02 is inadvertently de-energized by opening NB0209, NB02 MN FDR BKR FROM XNB02.

NB0211, NB02 EMERG FEED FROM B STBY DG NE02, closes re-energizing NB02 from NE02.

A CSAS actuates at the same time NB0211 closes.

Which ONE of the following correctly states the time at which the Containment Spray Pumps will start?

'A' CS Pump 'B' CS Pump A. Immediately Immediately B. Immediately 15 seconds C. 15 seconds 15 seconds D. 15 seconds 40 seconds

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 29 The plant is in Mode 1 at 75% reactor power.

Which ONE of the following is a correct IMMEDIATE ACTION for a main feed pump trip under these conditions per OTO-AE-00001, Feedwater System Malfunction?

A. Manually trip the reactor and enter E-0, Reactor Trip or Safety Injection.

B. Quickly run back turbine generator load to less than 60% or 750 MWe.

C. Use normal boration/adjust turbine load as necessary to match Tave and Tref.

D. Restore steam generator level to the program level of 50%.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 30 Which ONE of the following describes the operation of the Main Turbine Steam Valves during Control Valve Chest Warming?

A. Main Stop Valve #2 Bypass is Open.

B. All Intermediate Stop Valves are Shut.

C. Control Valves #1, #2 and #3 are Open.

D. All Main Stop Valves are Open.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 31 The crew is responding to a plant transient and is currently in procedure ECA-1.2, "LOCA Outside Containment".

Why should operators wait some amount of time during each valve repositioning per this procedure?

A. Prevents overcurrent trips on valve motor breakers.

B. Allows system pressure to respond to repositioning.

C. Prevent valve motor overheating due to excessive operation.

D. To allow check on indications of leak in auxiliary building.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 32 The plant is in Mode 1, 100% power. An inadvertent Main Steam Line Isolation occurs resulting in a reactor trip.

Which ONE of the following correctly describes the steam generator response? (Assume no operator action.)

A. Rapid pressure increase causes steam generator levels to increase, steam generator PORVs and Safety Valves lift relieving the pressure, steam generator levels decrease and main feedwater level control increases feed to regain level.

B. Rapid pressure increase causes steam generator levels to increase, steam generator PORVs lift relieving the pressure, steam generator levels decrease and auxiliary feedwater will feed to regain level.

C. Rapid pressure increase causes steam generator levels to decrease, steam generator PORVs and Safety Valves lift to relieve the pressure, steam generator levels decrease and auxiliary feedwater will feed to regain level.

D. Rapid pressure increase causes steam generator levels to decrease, steam generator PORVs lift relieving the pressure, steam generator levels decrease and main feedwater level control increases feed to regain level.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 33 Which ONE of the following describes the containment atmosphere radiation monitors GT-RE-31 and GT-RE-32?

A. They sample containment via the hydrogen control system and are isolated from containment by a CIS A actuation.

B. They sample upstream of the containment isolation valves for the hydrogen control system and are NOT isolated by a CIS A actuation.

C. They sample between the containment isolation valves on the mini purge exhaust line and initiate a CPIS on high high activity.

D. They sample from the containment purge exhaust line outside containment and initiate a CPIS on high high activity.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 34 Which ONE of the following will occur during an Emergency Start (SIS) of the NE02 Diesel Generator coincident with a loss of the NK supply to the field flash circuit?

A. At 85 rpm, an initial diesel generator field flash will be attempted.

B. At 125 rpm, the low speed relay de-energizes the starting air solenoids.

C. At 471 rpm, the high speed relay will attempt a redundant field flash.

D. At 514 rpm, the "At Voltage - At Frequency" white lights will illuminate.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 35 The following plant conditions exist:

The plant is in Mode 5

Midloop operations are in progress

SG hot and cold leg manway covers are removed

SG nozzle dams are installed in the hot legs

SG nozzle dams are NOT installed on the cold legs

Loss of RHR cooling occurs Which ONE of the following could occur as a result of this event?

A. Steam formation in the hot leg will cause an erroneously low RCS Loop Level indication.

B. Steam formation in the reactor vessel head will displace water from the reactor vessel and force water out the cold leg manways.

C. Steam formation in the reactor vessel head will increase RCS pressure and blow out the hot leg nozzle dams.

D. Steam formation in the hot leg will ultimately collapse, resulting in severe water hammer.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 36 The following plant conditions exist:

NCP is running, 120 gpm letdown.

BGFT121, CVCS CHG HDR TO REGEN HX FLOW XMTR, fails.

As a result, BGFCV124 closes.

The NCP handswitch red light is lit.

BGHV8109, NCP Recirculation Valve, is open.

The following annunciators are received:

CHARGING LINE FLOW LOW

SEAL INJECTION TO RCP FLOW LOW

NCP FLOW LOW Which ONE of the following actions should be taken immediately?

A. Take manual control of BGFCV124 and open it.

B. Start a CCP and secure the NCP.

C. Open BGHV8357A or B to restore seal injection.

D. Close all letdown orifice isolation valves.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 37 The following plant conditions exist:

Mode 1, 100% Reactor Power

Both Trains of ESW - normal standby lineup The normal feeder breaker to XNB02 is accidentally tripped OPEN by a Janitor/Groundskeeper working in the area. When the 'B' MDAFP pump started, a fault occurred resulting in a loss of NB02.

Which ONE of the following describes the response of the 'A' ESW Train to this event?

A. 'A" ESW pump AUTOMATICALLY STARTS - valve(s) in the 'A' ESW Train will reposition to provide a flowpath.

B. 'A' ESW pump AUTOMATICALLY STARTS - 'B' Train powered valve(s) in the 'A' ESW Train must be locally manually repositioned to provide a flowpath for 'A' Train.

C. 'A' ESW pump must be MANUALLY STARTED - valve(s) in the 'A' ESW Train will reposition to provide a flowpath.

D. 'A' ESW pump must be MANUALLY STARTED - 'B' Train powered valve(s) in the 'A' ESW Train must be locally manually repositioned to provide a flowpath for 'A' Train.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 38 The following plant conditions exist:

An RCS pipe break has occurred.

The crew is currently in ES-1.2, Post LOCA Cooldown and Depressurization, attempting to isolate SI Accumulators.

EPHV8808A, 'A' SI Accumulator Outlet Valve, will not close.

Which ONE of the following describes how the operators should address the stuck open 'A' SI Accumulator Outlet Valve?

A. Vent the 'A' SI Accumulator to the CTMT building.

B. Continue the cooldown and allow the SI Accumulator to discharge.

C. Dispatch an operator to close the valve locally.

D. Drain the 'A' SI Accumulator to the Reactor Coolant Drain Tank.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 39 The plant was initially in Mode 1. The following plant conditions now exist:

A large break LOCA has occurred inside Containment

Only the 'B' Train of Safety Injection AUTOMATICALLY ACTUATED

Train 'A' ECCS components have been STARTED/OPERATED MANUALLY

RWST level is 35% and DECREASING

'B' Train RHR Ctmt Recirc Sump Suction Valve, EJ HV-8811B, is OPEN

'A' Train RHR Ctmt Recirc Sump Suction Valve, EJ HV-8811A, is CLOSED Which ONE of the following describes why the 'A' RHR Pump must be temporarily STOPPED to complete the switchover to the Cold Leg Recirculation mode of ECCS?

A. RHR System Hot Leg Recirculation Valve, EJ HV-8716A, must be CLOSED in order to OPEN RHR Ctmt Recirculation Sump Suction Valve, EJ HV-8811A.

B. RWST to RHR Pump Suction Valve, BN HV-8812A, must be CLOSED in order to OPEN Ctmt Recirculation Sump Suction Valve, EJ HV-8811A.

C. RWST to RHR Pump Suction Valve, BN HV-8812A, must be CLOSED in order to OPEN RHR to Charging Pump Valve, EJ HV-8804A.

D. RHR to Accumulator Injection Valve, EJ HV-8809A, must be CLOSED in order to OPEN RHR Ctmt Recirculation Sump Suction Valve, EJ HV-8811A.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 40 The plant has been shutdown for 10 days and is in a refueling outage. One third of the core has been off-loaded to the Spent Fuel Pool. An accident has caused damage to the Spent Fuel Pool and level is DECREASING uncontrollably. The fuel transfer tube has been ISOLATED. The only source of makeup is Essential Service Water, which can just keep up with the leak.

Which ONE of the following is correct?

A. The Shutdown Margin in the Spent Fuel Pool will continue to DECREASE with eventual criticality being obtained in the Spent Fuel Pool.

B. The Shutdown Margin in both the Spent Fuel Pool and the Reactor Cavity will DECREASE until criticality is obtained in both the Spent Fuel Pool and the Reactor.

C. The Shutdown Margin in the Spent Fuel Pool will DECREASE but criticality will NOT be obtained because the fuel is depleted.

D. The Shutdown Margin in the Spent Fuel Pool will continue to DECREASE but criticality will NOT be obtained because of the fuel storage geometry.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 41 The plant is in Mode 4. A plant cooldown is in progress with RHR Train 'A' in a cooldown lineup. The Reactor Operator is directed to stop the plant cooldown. The Reactor Operator then CLOSES EGHV0101, 'A' CCW to 'A' RHR Hx.

Which ONE of the following events occur?

A. 'A' CCW flashes in the 'A' RHR heat exchanger causing the 'A' CCW surge tank level to increase.

B. 'A' ESW flashes in the 'A' CCW heat exchanger causing a water hammer in 'A' ESW.

C. 'A' RHR flashes in the 'A' RHR heat exchanger causing the 'A' RHR suction relief to lift.

D. 'A' ESW flashes in the 'A' CCW heat exchanger causing the heat exchanger tube side relief valve to lift.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 42 The plant is operating at 100% power with normal operating temperature and pressure when a pressurizer safety valve inadvertently lifts. The PRT pressure is 20 psig.

Which ONE of the following describes the condition of the steam entering the PRT?

A. Superheated steam at 668°F.

B. Superheated steam at 653°F C. Saturated steam/water mixture at 259°F.

D. Saturated steam/water mixture at 228°F.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 43 The following plant conditions exist:

Mode 1, 17% power, plant startup in progress.

'A' MFP is in AUTO.

ABUS0500Z, Steam Dump Selector Switch, is selected to STEAM PRESSURE mode.

ABPT0507, Main Steam Header Pressure, fails HIGH.

Which ONE of the following correctly describes the plant response?

A. Feed Pump speed will INCREASE. Steam Dumps will CLOSE, and will not reopen until the Steam Dump Mode Selector switch is placed in TAVG mode.

B. Feed Pump speed will DECREASE. Steam Dumps will CLOSE, and will not reopen until both Steam Dump Interlock Selector switches are RESET.

C. Feed Pump speed will INCREASE. Steam Dumps will OPEN, and will not close until one Steam Dump Interlock Selector switch is placed in OFF.

D. Feed Pump speed will DECREASE. Steam Dumps will OPEN, and will not close until ABPK0507, Steam Header Pressure Controller, is placed in MANUAL.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 44 The following plant conditions exist:

Large Break LOCA in progress

Crew is performing FR-Z.1, Response To High Containment Pressure, due to an ORANGE path on Containment Pressure

CTMT Pressure is 31 psig and INCREASING

Annunciator 47C, RWST LEV LOLO 1 AUTO XFR, has just ACTUATED Which ONE of the following should be performed?

A. CONTINUE in FR-Z.1, when completed, transition to ES-1.3, Transfer To Cold Leg Recirculation. Upon completion transition to E-1, Loss of Reactor or Secondary Coolant.

B. CONTINUE in FR-Z.1 until Containment Pressure is LESS THAN 25 psig, then transition to ES-1.3, Transfer to Cold Leg Recirculation.

C. SUSPEND performance of FR-Z.1, transition to ES-1.3, Transfer To Cold Leg Recirculation. Upon completion return to FR-Z.1.

D. SUSPEND performance of FR-Z.1, transition to ES-1.3, Transfer To Cold Leg Recirculation. Complete ES-1.3 through Step 3, then return to FR-Z.1.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 45 Which ONE of the following statements describes the effect of a loss of DC control power to 4160 VAC breaker NB0112, NB01 MN FDR BKR FROM XNB01? (Assume that the breaker is the only component affected by the loss of DC power.)

A. The breaker will fail in its current position and cannot be tripped or closed from the MCB.

B. The breaker will fail in its current position and can be tripped but not closed from the MCB.

C. The breaker will trip and can be closed but not tripped from the MCB.

D. The breaker will trip and cannot be tripped or closed from the MCB.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 46 The plant was at 100% power when a control rod located near the outside of the core drops fully into the core. The plant is stabilized at 93% power.

Which ONE of the following correctly indicates the most affected power distribution parameter AND at what time after the rod drop that core parameter is expected to be closest to its associated Technical Specification limit?

(Assume no other changes in plant status.)

Power Distribution Parameter Time Following Rod Drop A. Axial Flux Difference Immediately B. Quadrant Power Tilt Ratio Immediately C. Axial Flux Difference 4-6 hours D. Quadrant Power Tilt Ratio 4-6 hours

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 47 The following plant conditions exist:

Mode 4 with a cooldown in progress per OTG-ZZ-00004, Plant Cooldown Hot Standby to Cold Shutdown

'B' RHR train is to be placed in a cooldown lineup per OTN-EJ-00001, Residual Heat Removal System Which ONE of the following will prevent OPENING EJ-HV-8701B, RHR Pump 'B' Suct Iso?

A. EMHV8814B, SI Pump 'B' Recirc to RWST Iso, OPEN.

B. BBPI0405, RCS Wide Range Press Xmtr, reading 306 psig.

C. EJHV8811B, CTMT Recirc Sump 'B' to RHR Pump 'B' Suct Iso, OPEN.

D. BNHV8812B, RWST to RHR Pump 'B' Suct Iso Vlv, CLOSED.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 48 The following plant conditions exist:

Reactor has tripped

Safety Injection has actuated

All equipment has actuated per design

GE RE-92 Hi Hi alarm

'B' S/G NR Level 5% and INCREASING with AFW ISOLATED

'C' S/G pressure DECREASING in an uncontrolled manner Which ONE of the following describes the positions of the steam supply valves to the Turbine Driven AFW Pump after all Emergency Procedure actions have been completed?

'B' S/G 'C' S/G ABV0085 ABV0087 A. OPEN OPEN B. OPEN CLOSED C. CLOSED OPEN D. CLOSED CLOSED

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 49 The following plant conditions exist:

CTMT Shutdown Purge Exhaust Fan ON

CTMT Shutdown Purge Supply Fan OFF

CTMT Personnel Hatches both OPEN (interlocks defeated)

CTMT Equipment Hatch OPEN The CTMT Coordinator has identified a positive air flow from CTMT to the outside atmosphere through the equipment hatch.

Which ONE of the following actions is required for this condition?

A. Manually actuate a Containment Purge Isolation Signal.

B. Manually actuate a Control Room Ventilation Isolation Signal.

C. Shift the Auxiliary Building Normal Exhaust Fans to Fast Speed.

D. Start at least one train of Fuel Building/Auxiliary Building Emergency Exhaust.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 50 The crew has implemented FR-C.1, Response to Inadequate Core Cooling.

Which ONE of the following combinations of core exit thermocouples (TC's) and indicated temperatures would require starting RCP's, even if the normally required support conditions could not be met?

of TC's Indicated Temp A. 2 2450°F B. 4 1750°F C. 6 1350 °F D. 8 750°F

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 51 Which ONE of the following Area Radiation Monitors is required by the Final Safety Analysis Report (FSAR)?

A. SDRE0027, CTMT Purge Filter Unit B. SDRE0033, Control Room C. SDRE0037, Spent Fuel Pool D. SDRE0041, Manipulator Bridge

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 52 OTG-ZZ-00005, Plant Shutdown 20% Power to Hot Standby, requires the reactor operator to ensure proper sequence and overlap occurs as rods are inserted as specified in the COLR.

Which ONE of the following represents proper bank overlap for their respective bank?

Control Bank B Control Bank C A. 185 Steps 70 Steps B. 185 Steps 72 Steps C. 218 Steps 105 Steps D. 218 Steps 113 Steps

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 53 With the plant in Mode 3, the MCB handswitch for the Reactor Trip Breakers is rotated to the CLOSE position.

Which ONE of the below conditions would prevent the reactor trip breakers from closing?

A. Pressurizer level at 95%

B. RCS Pressure at 1800 psig C. Pressurizer Level at 17%

D. RCS Pressure at 2400 psig

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 54 The following plant conditions exist:

Mode 1, 12% Reactor Power

Power Ascension in progress

A fire occurs requiring an immediate evacuation of the control room.

The Operators are UNABLE to trip the reactor or perform the other IMMEDIATE ACTIONS of OTO-ZZ-00001, Control Room Inaccessibility, before exiting the control room.

Which ONE of the following actions will cause the Reactor Protection System to initiate a reactor trip?

A. Tripping the main turbine from the front standard.

B. Locally de-energizing PG19.

C. Tripping the normal feeder breaker to NB02.

D. Tripping all 4 RCP breakers at PA01 and PA02.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 55 A liquid radwaste release from Discharge Monitor Tank 'A' is in progress.

Which ONE of the following conditions would AUTOMATICALLY terminate the release?

A. Cooling tower blowdown flow rate is REDUCED to 6000 gpm.

B. RW bldg discharge rad monitor, HB RE-18, FAILS resulting in a Hi Hi alarm.

C. Steam generator blowdown surge tank level INCREASES to the Hi Hi setpoint.

D. A Hi Hi alarm on S/G blowdown discharge rad monitor causes BM FV-54 to CLOSE.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 56 A breaker fault in the NB01 Switchgear has resulted in a large fire. Installed Fire Suppression Systems have been ACTUATED.

Which ONE of the following describes how this fire will be extinguished?

A. Fire Brigade will apply foam to the fire.

B. Halon will be dumped into the room.

C. Carbon dioxide will be dumped into the room.

D. Deluge valve and sprinklers will actuate.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 57 Which ONE of the following sets of conditions would result in an actuation of the ATWS Mitigation System (AMSAC)? Consider ONLY the AMSAC System.

Elapsed First Stage Impulse Pressure S/G NR Level Time AC PT-505 AC PT-506 A. A-10% C-11% 40 sec. 100 psig 100 psig B-13% D-9%

B. A-9% C-10% 27 sec. 560 psig 565 psig B-8% D-9%

C. A-0% C-0% 21 sec. 760 psig 755 psig B-1% D-0%

D. A-10% C-13% 38 sec. 685 psig 690 psig B-14% D-11%

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 58 During the performance of ECA-0.0, Loss of All AC Power, battery NK11 discharge ammeter is reading 275 amps.

Which ONE of the following is the MAXIMUM time that NK01 could remain operable assuming the battery was fully charged initially?

A. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 59 The following plant conditions exist:

Mode 1, 100% power, all systems in a normal full power alignment.

AEPT508, Feed Pump Discharge Header Pressure, fails off scale HIGH.

Which ONE of the following is the expected INITIAL plant response?

A. Main Feedwater Pump speed increases.

B. Main Feedwater Pump speed decreases.

C. Main Feedwater Regulating Valves open.

D. Main Feedwater Regulating Valves close.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 60 A precaution and limitation in OTN-EG-00001, Component Cooling Water System, informs the operator that EGHV0069A/B (EG HS-69) and EGHV0070A/B (EG HS-70), CCW Supply/Return to Radwaste, must be opened simultaneously.

Which ONE of the following is the reason for this requirement?

A. Satisfy the system high flow interlock.

B. Satisfy the system low flow interlock.

C. Minimize potential of system water hammers.

D. Ensure proper flow is maintained to containment system loads.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 61 The following plant conditions exist:

A plant startup is in progress

The plant is at 9% power

Control Systems are in normal system alignment

The output of Power Range NI channel N44 gradually fails HIGH

No operator actions are taken Which ONE of the following is the INITIAL plant response?

A. OPT trip setpoint increases.

B. Steam generator levels increase.

C. Axial flux mismatch alarm illuminates.

D. Control rods will step in to maintain Tavg.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 62 A loss of condenser vacuum is occurring due to unknown reasons and power has been reduced from 100% to 75% over the last 5 minutes.

The following plant conditions exist:

Auct High Tavg 593°F

Reactor / Turbine Power 75% / 775 MWe

LP 'A' Condenser Pressure 5.8" Hga

LP 'B' Condenser Pressure 6.2" Hga

LP 'C' Condenser Pressure 6.5" Hga Which ONE of the following describes the expected operation of the condenser steam dumps with these conditions:

A. Less than 12 steam dumps are available and all available dumps are FULLY OPEN.

B. ALL 12 condenser steam dumps are available and all are FULLY OPEN.

C. Less than 12 steam dumps are available and all available dumps are PARTIALLY OPEN.

D. Less than 12 steam dumps are available and all are CLOSED.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 63 Which ONE of the following is a responsibility of the Reactor Operator in the Control Room during refueling operations?

A. Checking source range counts while a fuel assembly is being placed in the core.

B. Verifying proper operation of the Containment Evacuation alarm every shift.

C. Maintaining a 1/M plot while reloading fuel during a core shuffle.

D. Updating the temporary and final locations of all fuel assemblies using the PC program "SHUFFLE".

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 64 The following plant conditions exist:

The plant is at 7% power on the steam dumps to the condenser

Turbine rolling up to 1800 rpm

All operating Condensate Pumps TRIP Which ONE of the following describes the system response?

(ASSUME no operator action is taken.)

MFPs MDAFPs Reactor Trip A. Trip Start on S/G On S/G Low Low Level Low Low Level B. Do Not Trip Start on S/G On Turbine Low Low Level Trip C. Trip Start on MFW On S/G Pump Trip Low Low Level D. Do Not Trip Start on On Turbine Reactor Trip Trip

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 65 You are the on-duty Reactor Operator. In accordance with plant policy, which ONE of the following non-licensed individuals may you allow to start the 'A' Safety Injection (SI) Pump from Panel RL017 in the Control Room?

A. Any system engineer authorized by the Shift Supervisor who is performing SI system surveillances.

B. Any assistant equipment operator performing OJT on the SI system who is being monitored by the Control Room Supervisor.

C. Any individual who is in a license training program under my direct observation.

D. Any electrical maintenance supervisor troubleshooting why the SI pump vibration readings are abnormal.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 66 The plant is initially operating at 100%. A large Steam Line Rupture in Containment has resulted in the following:

CTMT Temperature is 180°F

CTMT Pressure is 8 psig Which ONE of the following describes the response of the Containment Coolers?

A. 'A' Containment Cooler supplies the Instrument Tunnel in FAST speed.

B. 'B' Containment Cooler supplies the Pressurizer Enclosure Compartment in SLOW speed.

C. 'C' Containment Cooler flows DIRECTLY to the containment atmosphere in SLOW speed.

D. 'D' Containment Cooler flows DIRECTLY to the containment atmosphere in FAST speed.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 67 Which ONE of the following red paths is MOST LIKELY to occur for a steam line break on a single S/G outside containment resulting in a Reactor Trip and Safety Injection? (Assume that all safeguards equipment functions as designed.)

A. Response to Imminent Pressurized Thermal Shock Condition (FR-P.1)

B. Response to Loss of Secondary Heat Sink (FR-H.1)

C. Response to Inadequate Core Cooling (FR-C.1)

D. Response to High Containment Pressure (FR-Z.1)

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 68 Which ONE of the following describes the affect on a Source Range Channel if the pulse height discriminator failed to a lower value?

The output would:

A. decrease due to the filtering which narrows the pulse height window.

B. decrease due to the removal of the higher amplitude neutron pulses.

C. increase due to the increased gamma interaction inside the detector.

D. increase due to counting of some of the lower amplitude gamma pulses.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 69 The following plant conditions exist:

Mode 1, 90% power, EOL

All systems are in a normal full power lineup

SEHS9, Rod Control Auto/Manual Select Switch, is in AUTO

Control Bank 'D' begins stepping in slowly Which ONE of the following events caused this response from rod control?

A. Regenerative Heat Exchanger tube leak.

B. Letdown Heat Exchanger tube leak.

C. Seal Water Heat Exchanger tube leak.

D. Excess Letdown Heat Exchanger tube leak.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 70 Which ONE of the following COULD cause the 'A' Train Subcooling Meter to indicate a SUPERHEATED condition?

A. Loop 3 Wide Range THOT fails LOW.

B. Wide Range Pressure Channel 403 fails LOW.

C. Loop 4 Wide Range TCOLD fails HIGH.

D. Wide Range Pressure Channel 405 fails HIGH.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 71 The plant is at 100% power with the following conditions:

'C' CCW pump OOS

'A' CCW Train in Service, 'B' CCW Train in Standby

NCP in Service with 120 gpm Letdown Flow The 'A' CCW pump trips due to unknown reasons.

Which ONE of the following includes required immediate actions?

A. Restart the 'A' CCW pump, if pump fails to restart, then start either 'B' or 'D' CCW pump and transfer the service loop to the 'B' CCW train.

B. Start either 'B' or 'D' CCW pump then transfer the service loop to the 'B' CCW train.

C. Trip the Reactor Coolant Pumps and the Reactor, enter E-0, Reactor Trip/Safety Injection, then transfer the service loop to the 'B' CCW train.

D. Verify 'B' CCW pump starts automatically then transfer the service loop to the 'B' CCW train.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 72 Which ONE of the following describes component status when the ESFAS Status Panel Component Level Window is DARK following actuation?

A. The component is NOT in its safeguards position, but is capable of being aligned.

B. A condition has PREVENTED the automatic operation of the component from its signal.

C. The component is DE-ENERGIZED and not capable of being aligned to its safeguards position.

D. The component has responded CORRECTLY to its emergency actuation signal.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 73 The following plant conditions exist:

The plant is in Mode 6

N43 is normalized to 100% for testing

Core Alterations are in progress

N31 indicates 150 cps

N32 indicates 165 cps Which ONE of the following automatic actions and required actions should occur if N42 were to fail HIGH?

A. Charging pumps suctions swap from the VCT to the RWST. Place the Flux Doubling Normal / Test Switch to the TEST position and re-align charging from the RWST.

B. Source Range NIs high voltage is de-energized. Suspend core alternations and positive reactivity changes; initiate action to restore one Source Range NI.

C. Containment Evacuation alarm sounds. Evacuate all unnecessary personnel from containment.

D. Fed Reg Bypass Valves fail CLOSED. Switch control to MANUAL and re-establish S/G levels.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 74 The following plant conditions exist:

Compressor Sequencer Selector Switch, KAHS0043, is selected to the CAB position.

All three air compressors are selected to AUTOMATIC.

'A' Air Compressor (CKA01A) is running unloaded.

'B' Air Compressor (CKA01B) is not running.

'C' Air Compressor (CKA01C) is running loaded.

KA-PV-11, Service Air Isolation Valve is open.

Which ONE of the following describes the correct system response to an air leak that results in air system pressure decreasing to 105 psig?

A. Only CKA01A and CKA01C are running and both are loaded.

B. All three air compressors are running, but only two are loaded.

C. Only CKA01A and CKA01C are running and both are loaded, KA-PV-11 is closed.

D. All three air compressors are running and all three are loaded, KA-PV-11 is closed.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 75 The following plant conditions exist:

VCT Automatic Makeup has failed.

The Reactor Operator has completed a MANUAL makeup to the VCT.

Approximately 15 minutes later, Control Bank "D" rods begin to INSERT slowly in automatic.

Tavg/Tref mismatch is +2°F.

Pzr level has increased approximately 1%.

Reactor power indicates 100.3% on all channels.

Which ONE of the following may have caused these indications?

A. The Total Flow Counter, BGFY111B, was inadvertently set too LOW.

B. The Boric Acid Counter, BGFY110B, was inadvertently set too LOW.

C. The Reactor Makeup Water Flow Controller, BGFK111, was inadvertently set too LOW.

D. The Boric Acid Flow Controller, BGFK110, was inadvertently set too HIGH.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 76 The plant has suffered a Loss of all AC Power.

Which ONE of the following sets of parameters indicates that natural circulation is occurring?

A. S/G Pressure 235 psig and STABLE, THOT 301°F and INCREASING.

B. S/G Pressure 435 psig and INCREASING, TCOLD 435°F and STABLE.

C. S/G Pressure 585 psig and INCREASING, THOT 530°F and DECREASING.

D. S/G Pressure 685 psig and STABLE, TCOLD 503°F and STABLE.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 77 The plant is in Mode 1 at 46% reactor power.

Which ONE of the following conditions will initiate a reactor trip?

A. 2 of 3 detectors on 2 of 4 loops indicating <90% RCS loop flow.

B. PA01 and PA02 bus frequency drops to 58 Hz for 2 seconds.

C. 2 of 3 detectors indicate 82% on pressurizer water level.

D. PA01 bus voltage drops to 12,000 volts for 0.5 seconds.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 78 The following plant conditions exist:

A fuel assembly has just been removed from the core

Immediately after initiating transit to the upender the refueling cavity level is reported to be a foot below normal and dropping at a visible rate Which ONE of the following is the preferred course of action?

A. Stop the fuel movement at the current location in the refueling pool.

B. Place the fuel assembly back into the reactor vessel.

C. Place the fuel assembly in the upender and lower it to the horizontal position.

D. Position the mast over the deepest part of the cavity and lower the assembly to the bottom.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 79 Technical Specifications require all full-length control rods to be OPERABLE in Modes 1 and 2 (with special test exceptions).

Which ONE of the following would cause a control rod to be INOPERABLE?

A. The CRDM stationary gripper coil turns OFF after the movable gripper coil turns ON during rod withdrawal.

B. The CRDM lift coil turns ON while the movable gripper coil is ON during rod withdrawal.

C. The CRDM lift coil turns ON and then the movable gripper coil turns ON during rod insertion.

D. The CRDM stationary gripper coil turns OFF before the movable gripper coil turns ON during rod insertion.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 80 The following plant conditions exist:

Rod H-8 in Control Bank "D" (CB D) was misaligned low.

Rod H-8 was withdrawn 15 steps to align it with the other rods in CB D.

The P/A converter AUTO/MAN switch was broke in the Auto position.

Which ONE of the following conditions occurs because of the P/A converter being in AUTO when rod H-8 was recovered?

A. Rod Control Non-Urgent Failure alarm when CB D rods initially moved in.

B. Rod Control Urgent Failure alarm when CB D initially moved in.

C. Rod Bank Lo alarm will be received with CB D actually above setpoint.

D. Rod Bank Lo alarm will be received with CB D actually below setpoint.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 81 A periodic load test is being performed on NE02, Standby Diesel Generator 'B' in accordance with OSP-NE-00001B. NE02 has been paralleled with 4160V Bus NB02 and is carrying 6 MW of real load. A Main Steamline break occurs and containment pressure increases to 20 (twenty) psig.

Which ONE of the following describes the response of the Load Shedding Emergency Load Sequencing System (LSELS)?

A. The LOCA Sequencer starts the Containment Spray Pumps at Step 3 (Time 15 seconds).

B. The Shutdown Sequencer starts the 'A' Essential Service Water Pump at Step 5 (Time 25 seconds).

C. The LOCA Sequencer starts the Safety Injection Pumps at Step 1 (Time 5 seconds).

D. The Shutdown Sequencer starts the Residual Heat Removal Pumps at Step 2 (Time 10 seconds).

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 82 The plant is at 100% power with all systems in their normal lineups. Annunciator 14A, S/U XFMR LOCKOUT, alarms due to failure of the Startup Transformer (SUT).

Which ONE of the following occurs as a result of the SUT failure?

A. A load shed occurs on NB01 and NB02.

B. Both emergency diesels NE01 and NE02 start.

C. An automatic Reactor Trip and Turbine Trip actuates.

D. Both the normal and alternate feeder breakers to NB02 trip.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 83 The following plant conditions exist:

At 0830, a loss of all offsite power occurred.

At 0845, a Safety Injection occurred due to a faulted S/G.

All equipment has operated as designed.

Restoration of instrument air to containment is in progress.

EFHV43 and EFHV44, ESW to 'A' and 'B' air compressors, are closed.

Which ONE of the following has caused EFHV43 and EFHV44 to close?

A. Loss of Instrument Air.

B. Blackout Load Shed.

C. LOCA Load Shed.

D. High D/P.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 84 The plant is in Mode 1 at 25% reactor power. Which ONE of the following would cause the crew to enter E-0, Reactor Trip or Safety Injection?

A. 'A' Steam Generator level is at 10% on all channels and the reactor has not tripped.

B. The main turbine stop valves have closed and the reactor has not tripped.

C. Pressurizer level channel 459 is at 98% and the reactor has not tripped.

D. 'C' RCP breaker has just tripped open and the reactor has not tripped.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 85 The plant has sustained an ATWS. The crew has entered FR-S.1, Response to Nuclear Power Generation. The BOP operator was unable to trip the turbine by pressing the Manual Turbine Trip pushbutton.

Which ONE of the following actions should the BOP operator attempt next?

A. Manually run back the turbine.

B. Fast close MSIVs and bypass valves.

C. Open the generator output breakers.

D. Check the AFW pumps running.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 86 The following plant conditions exist:

'A' and 'B' CCW Pumps are running.

The Service Loop is being supplied by 'B' CCW train.

'A' Component Cooling Water Radiation Monitor EGRE0009 has exceeded the Hi Hi ALARM setpoint.

Which ONE of the following automatic actions occur in addition to receiving an audible ALARM on the RM-11?

A. EGRV0009, CCW SRG TK A VENT CTRL VLV remains OPEN, EGRV0010, CCW SRG TK B VENT CTRL VLV remains OPEN.

B. EGRV0009, CCW SRG TK A VENT CTRL VLV remains OPEN, EGRV0010, CCW SRG TK B VENT CTRL VLV CLOSES.

C. EGRV0009, CCW SRG TK A VENT CTRL VLV CLOSES, EGRV0010, CCW SRG TK B VENT CTRL VLV remains OPEN.

D. EGRV0009, CCW SRG TK A VENT CTRL VLV CLOSES, EGRV0010, CCW SRG TK B VENT CTRL VLV CLOSES.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 87 The Callaway Plant is operating at 30% power and it is necessary to secure the 'B' Reactor Coolant Pump due to high vibration. After the RCP is tripped, the 'B' Loop T

_________________ and the other Loop Ts _________________. (Assume unit load is held constant.)

A. Increases, Decrease B. Increases; Increase C. Decreases; Decrease D. Decreases; Increase

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 88 OTN-BB-00003, Reactor Coolant Pumps, permits two successive starts of a RCP (provided the motor is allowed to coast to a stop between starts).

Which ONE of the following describes the bases for the RCP starting limits?

Limit the number of RCP starts in a short period to time prevents damage to the:

A. RCP motor stator windings.

B. RCP breaker protection relays.

C. RCP breaker junction terminals.

D. RCP motor armature insulation.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 89 Which ONE of the following will prevent outward rod motion in MANUAL rod control?

A. Selected Turbine Impulse Pressure channel is reading 13% equivalent power.

B. Two T channels are within 3% of the overtemperature T trip setpoint.

C. Control Bank D rods are positioned at 222 steps.

D. One Power Range NI is reading 102%.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 90 The following plant conditions exist:

Reactor is in Mode 3 at 557°F Tavg and 2235 psig

Current RCS boron is 800 ppm

An ECP boron of 600 ppm is needed

The Reactor Makeup Mode Selector Switch, BG HS-25, is in DILUTE

The Total Flow Counter BG FY-111B is set for 130 gallons

A dilution is started

Pressurizer level control is in AUTOMATIC and the controlling channel, BG LT-459, fails LOW Which ONE of the following represents the long term impact on RCS boron concentration, assuming NO operator actions are taken?

A. The boron will approach 600 ppm based on the FCV-110A control setpoint.

B. The boron will be slightly LESS than 800 ppm based on the 130 gallon dilution.

C. The boron will be HIGHER than 800 ppm based on a LOW pressure SI shifting charging suction to RWST.

D. The boron will be HIGHER than 800 ppm based on an AUTO swap to the RWST on low VCT level.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 91 A Callaway Plant employee has discovered a fire. Life safety is not threatened.

Which ONE of the following would be the correct actions of plant personnel?

A. First attempt to extinguish using any available fire fighting equipment, then call the Control Room.

B. First notify Control Room, then use any available fire fighting equipment, then report to your supervisor.

C. First notify Control Room, then use closest available extinguisher (if practical), then report to Fire Brigade Leader.

D. First attempt to extinguish the fire using closest available extinguisher (if practical),

then report to Fire Brigade Leader.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 92 The following plant conditions exist:

Pressurizer Pressure is 1600 psig

CTMT Pressure is 18 psig

CTMT Radiation is 13 R/hr and increasing

All S/G Pressures are 900 psig

No operator actions have been performed Which ONE of the following ESFAS Actuations should have automatically actuated?

A. SLIS and CRVIS B. SIS and CISB C. CRVIS and BSPIS D. CSAS and SIS

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 93 Which ONE of the following is an entry condition for OTO-ZZ-00003, Loss of Shutdown Margin?

A. Mode 3, following Reactor Trip at 0950 and RCS Tavg 545°F at 1115.

B. Mode 2, with Reactor Power at 5% and Control Bank C at 35 steps.

C. Mode 3, with RCS temperature decrease of 100°F in 20 minutes with ECCS operating in the Injection phase.

D. Mode 5, with Shutdown Margin Calculation indicating the core net reactivity of -1100 pcm.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 94 The following plant conditions exist:

Reactor power 80%

Rod control is in manual

All other controls are in automatic

All parameters are stable; Xenon, Tavg, turbine load, PZR level, SG pressure, reactor power Emergency boration is performed for TWO (2) minutes.

Assuming NO operator actions, which ONE of the following is the parameter that will return to its original value when steady state conditions are attained?

A. RCS Tavg B. PZR level C. SG pressure D. Reactor power

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 95 The following plant conditions exist:

The plant is in Mode 4

RCS temperature is 205°F

RCS pressure is 340 psig

RHR is in service

An unisolable leak in the Instrument Air system has occurred

Instrument Air system pressure is 60 psig and DECREASING Which ONE of the following describes how the RHR System will respond?

A. RHR Heat Exchanger Bypass Valves EJ FCV-618 & 619 will fail OPEN and cause RCS temperature to DECREASE.

B. RHR Heat Exchanger Bypass Valves EJ FCV-618 & 619 will fail CLOSED and cause RCS temperature to INCREASE.

C. RHR Heat Exchanger Flow Control Valves EJ HCV-606 & 607 will fail OPEN and cause RCS temperature to DECREASE.

D. RHR Heat Exchanger Flow Control Valves EJ HCV-606 & 607 will fail CLOSED and cause RCS temperature to INCREASE.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 96 The following plant conditions exist:

The unit is at 100% power with all systems aligned normally

The switchyard is in its preferred lineup with Ring Bus Breakers 52-2 and 52-3 CLOSED

A lockout occurs on 345KV Swyd Bus 'B' Which ONE of the following describes the response of the Containment Cooling Fans?

A. All fans CONTINUE to RUN in the PRESELECTED speed.

B. A & C fans are SHIFTED to SLOW speed by the shutdown sequencer.

C. B & D fans DE-ENERGIZE and are RESTARTED in FAST speed by the shutdown sequencer.

D. A & C fans DE-ENERGIZE and are RESTARTED in the PRESELECTED speed by the shutdown sequencer.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 97 A Pressurizer Pressure instrument has failed low. All immediate and subsequent operator actions have been completed for the failed instrument per OTO-BB-00006, Pressurizer Pressure Channel Failure.

Which ONE of the following remains INACCURATE despite the fact that the alternate instruments have been selected?

(Assume NO actions have been performed by I&C personnel.)

A. Pressurizer Pressure Control B. Pressurizer Pressure Recorder C. OPT/OTT Temp Recorder D. Core Subcooling Monitor

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 98 The following plant conditions exist:

Power range channel N-41 = 9%

Power range channel N-42 = 11%

Power range channel N-43 = 8%

Power range channel N-44 = 8%

Reactor shutdown is in progress The Reactor Operator inadvertently depresses the UNBLOCK pushbutton on SEHS-10, SR Trip BLOC/UNBLOCK for source range channel N32.

Which ONE of the following describes the status of the Source Range Nuclear Instruments?

A. Source Range Channels N31 and N32 will remain DE-ENERGIZED due to P-10.

B. Source Range Channel N31 remains DE-ENERGIZED and N32 will ENERGIZE.

C. Source Range Channels N31 and N32 will ENERGIZE.

D. Source Range Channels N31 and N32 will ENERGIZE while the switch is depressed, then DE-ENERGIZE when the switch is released.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 99 The following plant conditions exist:

Mode 3 following a manual Reactor Trip and Safety Injection

RCS pressure 1600 psig and STABLE

Average of the 10 highest reading Core Exit Thermocouples is 580°F

Pressurizer level 20% and INCREASING at 0.5% per minute

Containment temperature 140°F

Containment radiation 7 R/hr

S/G narrow range levels: 22%, 10%, 10%, 21%

AFW flow: 50,000 lbm/hr to each S/G The Control Room Supervisor is at Step 6 of E-1, Loss of Reactor or Secondary Coolant, and is trying to determine if ECCS flow should be REDUCED.

Which ONE of the following operator actions is appropriate for the above conditions? (Use E-1 Attachment 2, RCS Subcooling Curves, on the following page.)

A. SI termination criteria is met and transition should be made to ES-1.1, SI Termination.

B. SI termination criteria is NOT met since RCS subcooling is less than the required value, and further actions in E-1 are to be performed.

C. SI termination criteria is met if AFW flow is adjusted to > 300,000 lbm/hr. Do NOT transition to ES-1.1, SI Termination, until AFW flow is adjusted.

D. SI termination criteria is NOT met since pressurizer level is still low and further actions in E-1 are to be performed.

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 99 (continued)

AUGUST 2002 NRC RO WRITTEN EXAM QUESTION: 100 The following plant conditions exist:

The plant has sustained a transient event

All S/G pressures have increased

All 20 S/G safety valves are open Which ONE of the following is the LOWEST Main Feedwater Pump discharge pressure necessary to provide flow to the S/Gs?

A. 1126 psig B. 1186 psig C. 1223 psig D. 1235 psig

CALLAWAY PLANT EXAMINATION COVER SHEET TRAINING DEPARTMENT COURSE TITLE: SRO INITIAL LICENSE EXAMINATION DATE:

NAME (Print): SCORING:

SIGNATURE: Points Possible: 100 Points Missed:

Grade:

DIRECTIONS: BLACK OUT CORRECT ANSWERS

1. A B C D 26. A B C D 51. A B C D 76. A B C D

2. A B C D 27. A B C D 52. A B C D 77. A B C D

3. A B C D 28. A B C D 53. A B C D 78. A B C D

4. A B C D 29. A B C D 54. A B C D 79. A B C D

5. A B C D 30. A B C D 55. A B C D 80. A B C D

6. A B C D 31. A B C D 56. A B C D 81. A B C D

7. A B C D 32. A B C D 57. A B C D 82. A B C D

8. A B C D 33. A B C D 58. A B C D 83. A B C D

9. A B C D 34. A B C D 59. A B C D 84. A B C D

10. A B C D 35. A B C D 60. A B C D 85. A B C D

11. A B C D 36. A B C D 61. A B C D 86. A B C D

12. A B C D 37. A B C D 62. A B C D 87. A B C D

13. A B C D 38. A B C D 63. A B C D 88. A B C D

14. A B C D 39. A B C D 64. A B C D 89. A B C D

15. A B C D 40. A B C D 65. A B C D 90. A B C D

16. A B C D 41. A B C D 66. A B C D 91. A B C D

17. A B C D 42. A B C D 67. A B C D 92. A B C D

18. A B C D 43. A B C D 68. A B C D 93. A B C D

19. A B C D 44. A B C D 69. A B C D 94. A B C D

20. A B C D 45. A B C D 70. A B C D 95. A B C D

21. A B C D 46. A B C D 71. A B C D 96. A B C D

22. A B C D 47. A B C D 72. A B C D 97. A B C D

23. A B C D 48. A B C D 73. A B C D 98. A B C D

24. A B C D 49. A B C D 74. A B C D 99. A B C D

25. A B C D 50. A B C D 75. A B C D 100. A B C D

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 1 A permit required confined space entry is to be conducted at the Water Treatment Plant blowdown line manhole.

Which ONE of the following is true regarding this entry?

A. The attendant may enter the space if necessary, to rescue the entrant.

B. The work supervisor must be present whenever personnel are in the confined space.

C. Each entrant shall use a chest or full body harness.

D. The Medical Emergency Response Team will perform any emergency rescue if necessary.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 2 The plant is in Mode 1. CTMT Mini Purge system has been in service since 1407. At 1437, CTMT Mini Purge was secured due to the supply fan tripping. The fan problem has been corrected and it is desired to restart the CTMT Mini Purge.

Which ONE of the following is the LATEST time in which the CTMT Mini Purge can be restarted without requiring HP to resample CTMT atmosphere and generate a new release permit?

A. 1607 B. 1637 C. 1707 D. 1737

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 3 Which ONE of the following is a Technical Specification bases for observing that the RCCAs are positioned above their respective insertion limits during normal operation?

A. Ensures that assumptions for SDM and power distribution peaking factors are preserved.

B. Ensures that the trip instrumentation is within its normal operating range.

C. Ensures that the moderator temperature coefficient is within its analyzed range.

D. Ensures that the pressurizer is capable of being operable with a steam bubble.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 4 The following plant conditions exist:

A Loss of Coolant Accident has occurred

RWST level is 48%

Both RHR pumps tripped on overcurrent during SI actuation

All other equipment functioned as designed The crew is verifying Cold Leg Recirculation Capability per E-1, Loss of Reactor or Secondary Coolant, Attachment 5.

Which ONE of the following actions are required?

A. Transition to ECA-1.1, Loss of Emergency Coolant Recirculation.

B. Remain in E-1, Loss of Reactor or Secondary Coolant until directed to transition to ES-1.3, Transfer to Cold Leg Recirculation.

C. Transition to ES-1.3, Transfer to Cold Leg Recirculation, when RWST level reaches 36%.

D. Transition to ECA-1.2, LOCA Outside Containment.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 5 The following plant conditions exist:

Reactor power is 100%

Annunciator 78B, PR Upper Detector Flux Dev, is in alarm

Annunciator 78F, Power Range Tilt, is in alarm

The maximum QPTR is determined to be 1.04 Assuming QPTR is not reduced, within two hours reactor power must be reduced to at least

____?

A. 50%

B. 74%

C. 88%

D. 94%

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 6 OTN-BB-00003, Reactor Coolant Pumps, permits two successive starts of a RCP (provided the motor is allowed to coast to a stop between starts).

Which ONE of the following describes the bases for the RCP starting limits?

Limit the number of RCP starts in a short period to time prevents damage to the:

A. RCP motor stator windings.

B. RCP breaker protection relays.

C. RCP breaker junction terminals.

D. RCP motor armature insulation.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 7 Which ONE of the following red paths is MOST LIKELY to occur for a steam line break on a single S/G outside containment resulting in a Reactor Trip and Safety Injection? (Assume that all safeguards equipment functions as designed.)

A. Response to Imminent Pressurized Thermal Shock Condition (FR-P.1)

B. Response to Loss of Secondary Heat Sink (FR-H.1)

C. Response to Inadequate Core Cooling (FR-C.1)

D. Response to High Containment Pressure (FR-Z.1)

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 8 A breaker fault in the NB01 Switchgear has resulted in a large fire. Installed Fire Suppression Systems have been ACTUATED.

Which ONE of the following describes how this fire will be extinguished?

A. Fire Brigade will apply foam to the fire.

B. Halon will be dumped into the room.

C. Carbon dioxide will be dumped into the room.

D. Deluge valve and sprinklers will actuate.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 9 The plant was at 100% power when a control rod located near the outside of the core drops fully into the core. The plant is stabilized at 93% power.

Which ONE of the following correctly indicates the most affected power distribution parameter AND at what time after the rod drop that core parameter is expected to be closest to its associated Technical Specification limit?

(Assume no other changes in plant status.)

Power Distribution Parameter Time Following Rod Drop A. Axial Flux Difference Immediately B. Quadrant Power Tilt Ratio Immediately C. Axial Flux Difference 4-6 hours D. Quadrant Power Tilt Ratio 4-6 hours

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 10 The crew is responding to a plant transient and is currently in procedure ECA-1.2, "LOCA Outside Containment".

Why should operators wait some amount of time during each valve repositioning per this procedure?

A. Prevents overcurrent trips on valve motor breakers.

B. Allows system pressure to respond to repositioning.

C. Prevent valve motor overheating due to excessive operation.

D. To allow check on indications of leak in auxiliary building.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 11 The following plant conditions exist:

The plant is in Mode 6

N43 is normalized to 100% for testing

Core Alterations are in progress

N31 indicates 150 cps

N32 indicates 165 cps Which ONE of the following automatic actions and required actions should occur if N42 were to fail HIGH?

A. Charging pumps suctions swap from the VCT to the RWST. Place the Flux Doubling Normal / Test Switch to the TEST position and re-align charging from the RWST.

B. Source Range NIs high voltage is de-energized. Suspend core alternations and positive reactivity changes; initiate action to restore one Source Range NI.

C. Containment Evacuation alarm sounds. Evacuate all unnecessary personnel from containment.

D. Fed Reg Bypass Valves fail CLOSED. Switch control to MANUAL and re-establish S/G levels.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 12 Which ONE of the following will occur during an Emergency Start (SIS) of the NE02 Diesel Generator coincident with a loss of the NK supply to the field flash circuit?

A. At 85 rpm, an initial diesel generator field flash will be attempted.

B. At 125 rpm, the low speed relay de-energizes the starting air solenoids.

C. At 471 rpm, the high speed relay will attempt a redundant field flash.

D. At 514 rpm, the "At Voltage - At Frequency" white lights will illuminate.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 13 The following plant conditions exist:

VCT Automatic Makeup has failed.

The Reactor Operator has completed a MANUAL makeup to the VCT.

Approximately 15 minutes later, Control Bank "D" rods begin to INSERT slowly in automatic.

Tavg/Tref mismatch is +2°F.

Pzr level has increased approximately 1%.

Reactor power indicates 100.3% on all channels.

Which ONE of the following may have caused these indications?

A. The Total Flow Counter, BGFY111B, was inadvertently set too LOW.

B. The Boric Acid Counter, BGFY110B, was inadvertently set too LOW.

C. The Reactor Makeup Water Flow Controller, BGFK111, was inadvertently set too LOW.

D. The Boric Acid Flow Controller, BGFK110, was inadvertently set too HIGH.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 14 The following plant conditions exist:

Mode 1, 100% power, all equipment in a normal full power lineup

4A Low Pressure Feedwater Heater level instrumentation indicates Hi Hi level.

Which ONE of the following describes the effect on MAIN FEEDWATER?

A. Temperature increases.

B. Flow increases.

C. Temperature decreases.

D. Flow decreases.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 15 Which ONE of the following describes the plant response to a Hi Hi Radiation Alarm on GH RE-10B, Radwaste Building Exhaust Fans Discharge Header Radiation Monitor?

A. Radwaste Building Supply Unit (SGH01) STOPS.

B. Waste Gas Compressors (SHA02A & B) STOP.

C. Catalytic Hydrogen Recombiners (SHA01A & B) ISOLATE.

D. Gas Decay Tanks to RW HVAC Discharge Valve (HA HCV-14) ISOLATES.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 16 The following plant conditions exist:

Mode 1, 17% power, plant startup in progress.

'A' MFP is in AUTO.

ABUS0500Z, Steam Dump Selector Switch, is selected to STEAM PRESSURE mode.

ABPT0507, Main Steam Header Pressure, fails HIGH.

Which ONE of the following correctly describes the plant response?

A. Feed Pump speed will INCREASE. Steam Dumps will CLOSE, and will not reopen until the Steam Dump Mode Selector switch is placed in TAVG mode.

B. Feed Pump speed will DECREASE. Steam Dumps will CLOSE, and will not reopen until both Steam Dump Interlock Selector switches are RESET.

C. Feed Pump speed will INCREASE. Steam Dumps will OPEN, and will not close until one Steam Dump Interlock Selector switch is placed in OFF.

D. Feed Pump speed will DECREASE. Steam Dumps will OPEN, and will not close until ABPK0507, Steam Header Pressure Controller, is placed in MANUAL.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 17 The plant is at 100% power with all systems in their normal lineups. Annunciator 14A, S/U XFMR LOCKOUT, alarms due to failure of the Startup Transformer (SUT).

Which ONE of the following occurs as a result of the SUT failure?

A. A load shed occurs on NB01 and NB02.

B. Both emergency diesels NE01 and NE02 start.

C. An automatic Reactor Trip and Turbine Trip actuates.

D. Both the normal and alternate feeder breakers to NB02 trip.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 18 The following plant conditions exist:

Mode 1, 90% power, EOL

All systems are in a normal full power lineup

SEHS9, Rod Control Auto/Manual Select Switch, is in AUTO

Control Bank 'D' begins stepping in slowly Which ONE of the following events caused this response from rod control?

A. Regenerative Heat Exchanger tube leak.

B. Letdown Heat Exchanger tube leak.

C. Seal Water Heat Exchanger tube leak.

D. Excess Letdown Heat Exchanger tube leak.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 19 A precaution and limitation in OTN-EG-00001, Component Cooling Water System, informs the operator that EGHV0069A/B (EG HS-69) and EGHV0070A/B (EG HS-70), CCW Supply/Return to Radwaste, must be opened simultaneously.

Which ONE of the following is the reason for this requirement?

A. Satisfy the system high flow interlock.

B. Satisfy the system low flow interlock.

C. Minimize potential of system water hammers.

D. Ensure proper flow is maintained to containment system loads.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 20 An accessible area where an individual could receive a dose equivalent greater than

________________ in one hour at a distance 12 inches from the radiation source is classified as a ____________________.

A. 1000 mrem; CAUTION HIGH RADIATION AREA B. 100 mrem; RADIATION AREA C. 100 mrem; HOT SPOT D. 1000 mrem; DANGER HIGH RADIATION AREA

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 21 An ATWS has occurred and the crew is at step 6 of FR-S.1, Response to Nuclear Power Generation, when a safety injection occurs.

Which ONE of the following describes the correct actions to be taken?

A. Assign an RO to perform Attachment 12 of E-0 while continuing in FR-S.1.

B. Immediately exit FR-S.1 and implement E-0, Reactor Trip or Safety Injection.

C. Restart the Normal Charging Pump to re-initiate immediate boration.

D. Immediately after the reactor is verified tripped, exit FR-S.1 and implement E-0.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 22 The following plant conditions exist:

A large break LOCA has occurred

Containment pressure is 11 psig

Containment recirc sump level is 16 inches

Containment radiation level is 150 R/hr

RWST level is 56%

Which ONE of the following procedures should be utilized for the above conditions?

A. FR-Z.3, Response to High Containment Radiation Level.

B. FR-Z.2, Response to High Containment Recirc Sump Level.

C. FR-Z.1, Response to High Containment Pressure.

D. ES-1.3, Transfer to Cold Leg Recirculation

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 23 Which ONE of the following correctly describes the bases for CST Water Inventory required by Technical Specifications?

Ensure that sufficient cooling water is available to maintain _________.

A. Hot Shutdown for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months followed by a controlled cooldown to RHR entry conditions.

B. Hot Standby for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months followed by a controlled cooldown to RHR entry conditions.

C. Hot Standby for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months followed by a controlled cooldown to cold shutdown.

D. Hot Shutdown for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months followed by a controlled cooldown to cold shutdown.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 24 New fuel receipt is in progress in the Fuel Building. The Fuel Building rollup door is closed.

While lifting a new fuel storage cask containing 2 new fuel assemblies, a sling fails and the cask is dropped 47 feet to the truck bay floor.

Which ONE of the following describes the actions to be taken per OTO-KE-00001, Fuel Handling Accident?

A. Contact Reactor Engineer for guidance, evacuate unnecessary personnel from the Fuel Building, and manually initiate CPIS.

B. Contact Reactor Engineer for guidance, manually initiate FBIS, and manually initiate CRVIS.

C. Contact Reactor Engineer for guidance, evacuate unnecessary personnel from the Fuel Building, and manually initiate FBIS.

D. Manually initiate CPIS, manually initiate FBIS, and manually initiate CRVIS

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 25 The plant is in Mode 2. A Reactor Building entry is required for repair of a component.

Which ONE of the following the MAXIMUM number of personnel allowed in the Reactor Building?

A. 10 B. 15 C. 20 D. 25

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 26 Which ONE of the following is the basis for maintaining SG Narrow Range Level > 4% in at least one intact SG when depressurizing intact SGs to 220 psig in ECA-0.0, Loss of All AC Power?

A. Narrow Range Level is the only indication of SG inventory available after a Loss of All AC Power.

B. Ensures proper thermal stratification in the SGs in the event of a Steam Generator Tube Rupture.

C. Ensures the capability to cooldown once AC power is restored.

D. Ensures an adequate heat sink exists to remove heat from the RCS.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 27 The plant has suffered a Loss of all AC Power.

Which ONE of the following sets of parameters indicates that natural circulation is occurring?

A. S/G Pressure 235 psig and STABLE, THOT 301°F and INCREASING.

B. S/G Pressure 435 psig and INCREASING, TCOLD 435°F and STABLE.

C. S/G Pressure 585 psig and INCREASING, THOT 530°F and DECREASING.

D. S/G Pressure 685 psig and STABLE, TCOLD 503°F and STABLE.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 28 FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, is in progress.

Which ONE of the following conditions is acceptable using Attachment 7, on the following page, for RCS Post-Soak Cooldown Limitations during recovery from the PTS condition?

A. RCS cold legs = 200°F. RCS wide range pressure = 0 psig.

B. RCS cold legs = 250°F. RCS wide range pressure = 300 psig.

C. RCS cold legs = 300°F. RCS wide range pressure = 400 psig.

D. RCS cold legs = 400°F. RCS wide range pressure = 300 psig.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 28 (continued)

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 29 The following plant conditions exist:

Mode 1, 12% Reactor Power

Power Ascension in progress

A fire occurs requiring an immediate evacuation of the control room.

The Operators are UNABLE to trip the reactor or perform the other IMMEDIATE ACTIONS of OTO-ZZ-00001, Control Room Inaccessibility, before exiting the control room.

Which ONE of the following actions will cause the Reactor Protection System to initiate a reactor trip?

A. Tripping the main turbine from the front standard.

B. Locally de-energizing PG19.

C. Tripping the normal feeder breaker to NB02.

D. Tripping all 4 RCP breakers at PA01 and PA02.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 30 A reactor startup is in progress. Power level is at 1E-7 amps when a reactor trip occurs due to a Nuclear Instrumentation Channel failure.

Which ONE of the following is the approximate length of time before the Source Range NIs will automatically energize?

A. 2 minutes B. 5 minutes C. 10 minutes D. 15 minutes

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 31 The following plant conditions exist:

An RCS pipe break has occurred.

The crew is currently in ES-1.2, Post LOCA Cooldown and Depressurization, attempting to isolate SI Accumulators.

EPHV8808A, 'A' SI Accumulator Outlet Valve, will not close.

Which ONE of the following describes how the operators should address the stuck open 'A' SI Accumulator Outlet Valve?

A. Vent the 'A' SI Accumulator to the CTMT building.

B. Continue the cooldown and allow the SI Accumulator to discharge.

C. Dispatch an operator to close the valve locally.

D. Drain the 'A' SI Accumulator to the Reactor Coolant Drain Tank.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 32 A plant startup is in progress with power indicating 1E-8 amps on both channels of IR nuclear instruments.

Which ONE of the following will occur if IR channel N35 fails to 22%, current equivalent?

A. IR High Flux Reactor Trip.

B. IR Rod Stop will stop outward rod motion.

C. PR Low Flux Reactor Trip.

D. Pzr High Level Reactor Trip is unblocked.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 33 The following plant conditions exist:

Reactor is in Mode 3 at 557°F Tavg and 2235 psig

Current RCS boron is 800 ppm

An ECP boron of 600 ppm is needed

The Reactor Makeup Mode Selector Switch, BG HS-25, is in DILUTE

The Total Flow Counter BG FY-111B is set for 130 gallons

A dilution is started

Pressurizer level control is in AUTOMATIC and the controlling channel, BG LT-459, fails LOW Which ONE of the following represents the long term impact on RCS boron concentration, assuming NO operator actions are taken?

A. The boron will approach 600 ppm based on the FCV-110A control setpoint.

B. The boron will be slightly LESS than 800 ppm based on the 130 gallon dilution.

C. The boron will be HIGHER than 800 ppm based on a LOW pressure SI shifting charging suction to RWST.

D. The boron will be HIGHER than 800 ppm based on an AUTO swap to the RWST on low VCT level.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 34 The following plant conditions exist:

Pressurizer Pressure is 1600 psig

CTMT Pressure is 18 psig

CTMT Radiation is 13 R/hr and increasing

All S/G Pressures are 900 psig

No operator actions have been performed Which ONE of the following ESFAS Actuations should have automatically actuated?

A. SLIS and CRVIS B. SIS and CISB C. CRVIS and BSPIS D. CSAS and SIS

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 35 The following plant conditions exist:

A plant startup is in progress

The plant is at 9% power

Control Systems are in normal system alignment

The output of Power Range NI channel N44 gradually fails HIGH

No operator actions are taken Which ONE of the following is the INITIAL plant response?

A. OPT trip setpoint increases.

B. Steam generator levels increase.

C. Axial flux mismatch alarm illuminates.

D. Control rods will step in to maintain Tavg.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 36 Which ONE of the following Area Radiation Monitors is required by the Final Safety Analysis Report (FSAR)?

A. SDRE0027, CTMT Purge Filter Unit B. SDRE0033, Control Room C. SDRE0037, Spent Fuel Pool D. SDRE0041, Manipulator Bridge

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 37 The following plant conditions exist:

Safety Injection actuated on Low Pzr Pressure and has NOT been RESET.

CTMT pressure is 10 psig and increasing at 1 psig/minute.

NB01 is energized from off-site power.

NB02 is inadvertently de-energized by opening NB0209, NB02 MN FDR BKR FROM XNB02.

NB0211, NB02 EMERG FEED FROM B STBY DG NE02, closes re-energizing NB02 from NE02.

A CSAS actuates at the same time NB0211 closes.

Which ONE of the following correctly states the time at which the Containment Spray Pumps will start?

'A' CS Pump 'B' CS Pump A. Immediately Immediately B. Immediately 15 seconds C. 15 seconds 15 seconds D. 15 seconds 40 seconds

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 38 A periodic load test is being performed on NE02, Standby Diesel Generator 'B' in accordance with OSP-NE-00001B. NE02 has been paralleled with 4160V Bus NB02 and is carrying 6 MW of real load. A Main Steamline break occurs and containment pressure increases to 20 (twenty) psig.

Which ONE of the following describes the response of the Load Shedding Emergency Load Sequencing System (LSELS)?

A. The LOCA Sequencer starts the Containment Spray Pumps at Step 3 (Time 15 seconds).

B. The Shutdown Sequencer starts the 'A' Essential Service Water Pump at Step 5 (Time 25 seconds).

C. The LOCA Sequencer starts the Safety Injection Pumps at Step 1 (Time 5 seconds).

D. The Shutdown Sequencer starts the Residual Heat Removal Pumps at Step 2 (Time 10 seconds).

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 39 The following plant conditions exist:

The plant is in Mode 4

RCS temperature is 205°F

RCS pressure is 340 psig

RHR is in service

An unisolable leak in the Instrument Air system has occurred

Instrument Air system pressure is 60 psig and DECREASING Which ONE of the following describes how the RHR System will respond?

A. RHR Heat Exchanger Bypass Valves EJ FCV-618 & 619 will fail OPEN and cause RCS temperature to DECREASE.

B. RHR Heat Exchanger Bypass Valves EJ FCV-618 & 619 will fail CLOSED and cause RCS temperature to INCREASE.

C. RHR Heat Exchanger Flow Control Valves EJ HCV-606 & 607 will fail OPEN and cause RCS temperature to DECREASE.

D. RHR Heat Exchanger Flow Control Valves EJ HCV-606 & 607 will fail CLOSED and cause RCS temperature to INCREASE.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 40 Because of an administrative oversight OSP-NE-00001A, Standby Diesel Generator 'A' Periodic Tests (a Continuous Use Procedure) must be performed within the next 20 minutes to comply with the surveillance frequency requirements. The Secondary Equipment Operator reports that he CANNOT perform the Pre-Start Checks as required by the Initial Conditions in 20 minutes.

Which ONE of the following describes the action to be taken?

A. With SS permission, the diesel can be run without performing the Pre-Start Checks since it is always in standby and ready to start.

B. Generate a Temporary Change Notice for the Initial Conditions that removes the requirement for performing the Pre-Start Checks.

C. With SS permission, just perform selected portions of the Pre-Start checks so the diesel can be started within 20 minutes.

D. The Pre-Start Checks must be performed regardless of the time required to complete them.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 41 The following plant conditions exist:

Reactor has tripped

Safety Injection has actuated

All equipment has actuated per design

GE RE-92 Hi Hi alarm

'B' S/G NR Level 5% and INCREASING with AFW ISOLATED

'C' S/G pressure DECREASING in an uncontrolled manner Which ONE of the following describes the positions of the steam supply valves to the Turbine Driven AFW Pump after all Emergency Procedure actions have been completed?

'B' S/G 'C' S/G ABV0085 ABV0087 A. OPEN OPEN B. OPEN CLOSED C. CLOSED OPEN D. CLOSED CLOSED

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 42 The liquid radwaste discharge monitor, HB-RE-18, has been declared inoperable.

Which ONE of the following describes the actions that will permit discharging a Discharge Monitor Tank (DMT)?

A. The Superintendent, Rad Chem must approve the release permit.

B. The liquid release may continue up to 14 days with no further action.

C. Two independent samples of the DMT must be analyzed, and two technically qualified staff members must independently verify the release rate calculation and discharge valve lineup.

D. Samples must be taken every 30 minutes while the discharge is in progress to verify the effluent is within the FSAR discharge requirements.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 43 During the movement of irradiated fuel assemblies within containment, there must be a minimum of 23 feet of water above the top of the reactor vessel flange.

Which ONE of the following is the Technical Specification bases for this requirement?

A. To ensure adequate shielding for personnel who are working on the refueling bridge.

B. To retain iodine fission product activity in the water during fuel handling accident.

C. To provide sufficient subcooling to assure adequate natural circulation cooling.

D. To provide adequate net positive suction head for the RHR Pumps.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 44 The following plant conditions exist:

RCS Tave is 400°F

Pressurizer pressure is 2235 psig

Source Range NIs are 140 cps Which ONE of the following Class 1E 125 VDC system alignments will result in an operable NK bus?

A. Load Center NG01 to Swing Charger NK25 to bus NK04.

B. Load Center NG04 to Swing Charger NK26 to bus NK02.

C. Load Center PG20 to Swing Charger NK26 to bus NK03.

D. Load Center PG19 to Swing Charger NK25 to bus NK01

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 45 A steam line has ruptured inside containment resulting in a reactor trip and safety injection.

E-0, Reactor Trip or Safety Injection had been entered and the operating crew has transitioned to E-1, Loss of Reactor or Secondary Coolant. While monitoring the CSF status trees, you determine that an ORANGE path exists for SUBCRITICALITY.

Which ONE of the following actions should be performed by the crew?

A. Continue current pass through the status trees, if no RED path is encountered then implement FR-S.1.

B. Complete the actions of E-1, then implement FR-S.1.

C. Immediately implement FR-S.1, then continue current pass through the status trees.

D. Implement FR-S.1 at the discretion of the Shift Supervisor.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 46 Which ONE of the following conditions represents a loss of Containment Integrity per Technical Specifications?

A. While in Mode 1, an operator opens the outer door of the Containment Personnel Air Lock.

B. While in Mode 3, during an inspection of the equipment hatch, it is determined that the hatch is NOT sealed.

C. While in Mode 4, containment internal pressure is found to be 1.2 psig.

D. While in Mode 5, both containment emergency air lock doors are found open.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 47 Which ONE of the following is an entry condition for OTO-ZZ-00003, Loss of Shutdown Margin?

A. Mode 3, following Reactor Trip at 0950 and RCS Tavg 545°F at 1115.

B. Mode 2, with Reactor Power at 5% and Control Bank C at 35 steps.

C. Mode 3, with RCS temperature decrease of 100°F in 20 minutes with ECCS operating in the Injection phase.

D. Mode 5, with Shutdown Margin Calculation indicating the core net reactivity of -1100 pcm.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 48 A loss of condenser vacuum is occurring due to unknown reasons and power has been reduced from 100% to 75% over the last 5 minutes.

The following plant conditions exist:

Auct High Tavg 593°F

Reactor / Turbine Power 75% / 775 MWe

LP 'A' Condenser Pressure 5.8" Hga

LP 'B' Condenser Pressure 6.2" Hga

LP 'C' Condenser Pressure 6.5" Hga Which ONE of the following describes the expected operation of the condenser steam dumps with these conditions:

A. Less than 12 steam dumps are available and all available dumps are FULLY OPEN.

B. ALL 12 condenser steam dumps are available and all are FULLY OPEN.

C. Less than 12 steam dumps are available and all available dumps are PARTIALLY OPEN.

D. Less than 12 steam dumps are available and all are CLOSED.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 49 A large steam line break occurs inside containment. A Safety Injection occurs on Containment Pressure. Containment pressure is 30 psig when step 10 of Attachment 12 of E-0, "Check if CTMT Spray is Required", is performed.

Which ONE of the following is the reason for stopping all four RCP's?

A. They are an unnecessary addition of heat to Containment.

B. All RCP cooling water flow is automatically isolated.

C. Air is too dense for the motor cooler fans to keep the motor cool.

D. Containment structural failure is imminent.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 50 The plant is operating at 100% power with normal operating temperature and pressure when a pressurizer safety valve inadvertently lifts. The PRT pressure is 20 psig.

Which ONE of the following describes the condition of the steam entering the PRT?

A. Superheated steam at 668°F.

B. Superheated steam at 653°F C. Saturated steam/water mixture at 259°F.

D. Saturated steam/water mixture at 228°F.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 51 The following plant conditions exist:

Mode 3 following a manual Reactor Trip and Safety Injection

RCS pressure 1600 psig and STABLE

Average of the 10 highest reading Core Exit Thermocouples is 580°F

Pressurizer level 20% and INCREASING at 0.5% per minute

Containment temperature 140°F

Containment radiation 7 R/hr

S/G narrow range levels: 22%, 10%, 10%, 21%

AFW flow: 50,000 lbm/hr to each S/G The Control Room Supervisor is at Step 6 of E-1, Loss of Reactor or Secondary Coolant, and is trying to determine if ECCS flow should be REDUCED.

Which ONE of the following operator actions is appropriate for the above conditions? (Use E-1 Attachment 2, RCS Subcooling Curves, on the following page.)

A. SI termination criteria is met and transition should be made to ES-1.1, SI Termination.

B. SI termination criteria is NOT met since RCS subcooling is less than the required value, and further actions in E-1 are to be performed.

C. SI termination criteria is met if AFW flow is adjusted to > 300,000 lbm/hr. Do NOT transition to ES-1.1, SI Termination, until AFW flow is adjusted.

D. SI termination criteria is NOT met since pressurizer level is still low and further actions in E-1 are to be performed.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 51 (continued)

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 52 During normal operation, GERE92, Condenser Air Removal Rad Monitor alarms. A steam generator tube leak is suspected. Given the following information:

Charging Flow: 120 gpm

Letdown Flow: 75 gpm

Pressurizer Level: 57% and STABLE

Tavg: 584.4°F and STABLE

RCP Seal Injection Flow: 8 gpm per pump

RCP Seal Leakoff Flow: 3 gpm per pump Which ONE of the following is the approximate steam generator tube leakage rate?

A. 25 gpm B. 33 gpm C. 37 gpm D. 45 gpm

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 53 The following plant conditions exist:

At 0830, a loss of all offsite power occurred.

At 0845, a Safety Injection occurred due to a faulted S/G.

All equipment has operated as designed.

Restoration of instrument air to containment is in progress.

EFHV43 and EFHV44, ESW to 'A' and 'B' air compressors, are closed.

Which ONE of the following has caused EFHV43 and EFHV44 to close?

A. Loss of Instrument Air.

B. Blackout Load Shed.

C. LOCA Load Shed.

D. High D/P.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 54 Which ONE of the following COULD cause the 'A' Train Subcooling Meter to indicate a SUPERHEATED condition?

A. Loop 3 Wide Range THOT fails LOW.

B. Wide Range Pressure Channel 403 fails LOW.

C. Loop 4 Wide Range TCOLD fails HIGH.

D. Wide Range Pressure Channel 405 fails HIGH.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 55 The following plant conditions exist:

Mode 1, 100% power, all systems in a normal full power alignment.

AEPT508, Feed Pump Discharge Header Pressure, fails off scale HIGH.

Which ONE of the following is the expected INITIAL plant response?

A. Main Feedwater Pump speed increases.

B. Main Feedwater Pump speed decreases.

C. Main Feedwater Regulating Valves open.

D. Main Feedwater Regulating Valves close.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 56 Callaway Plant is in Mode 3 cooling down for a Refueling outage. The Reactor Operator has been directed to decrease RCS pressure to 1950 psig.

Which ONE of the following would the Reactor Operator have to set the Pressurizer Pressure Master Control, BBPK455A, to maintain the RCS at 1950 psig in Auto?

(Narrow Range Pzr Pressure range is from 1700 to 2500 psig.)

A. 1.77 turns B. 2.55 turns C. 3.13 turns D. 4.41 turns

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 57 The plant has been shutdown for 10 days and is in a refueling outage. One third of the core has been off-loaded to the Spent Fuel Pool. An accident has caused damage to the Spent Fuel Pool and level is DECREASING uncontrollably. The fuel transfer tube has been ISOLATED. The only source of makeup is Essential Service Water, which can just keep up with the leak.

Which ONE of the following is correct?

A. The Shutdown Margin in the Spent Fuel Pool will continue to DECREASE with eventual criticality being obtained in the Spent Fuel Pool.

B. The Shutdown Margin in both the Spent Fuel Pool and the Reactor Cavity will DECREASE until criticality is obtained in both the Spent Fuel Pool and the Reactor.

C. The Shutdown Margin in the Spent Fuel Pool will DECREASE but criticality will NOT be obtained because the fuel is depleted.

D. The Shutdown Margin in the Spent Fuel Pool will continue to DECREASE but criticality will NOT be obtained because of the fuel storage geometry.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 58 The following plant conditions exist:

'A' and 'B' CCW Pumps are running.

The Service Loop is being supplied by 'B' CCW train.

'A' Component Cooling Water Radiation Monitor EGRE0009 has exceeded the Hi Hi ALARM setpoint.

Which ONE of the following automatic actions occur in addition to receiving an audible ALARM on the RM-11?

A. EGRV0009, CCW SRG TK A VENT CTRL VLV remains OPEN, EGRV0010, CCW SRG TK B VENT CTRL VLV remains OPEN.

B. EGRV0009, CCW SRG TK A VENT CTRL VLV remains OPEN, EGRV0010, CCW SRG TK B VENT CTRL VLV CLOSES.

C. EGRV0009, CCW SRG TK A VENT CTRL VLV CLOSES, EGRV0010, CCW SRG TK B VENT CTRL VLV remains OPEN.

D. EGRV0009, CCW SRG TK A VENT CTRL VLV CLOSES, EGRV0010, CCW SRG TK B VENT CTRL VLV CLOSES.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 59 You are the on-duty Reactor Operator. In accordance with plant policy, which ONE of the following non-licensed individuals may you allow to start the 'A' Safety Injection (SI) Pump from Panel RL017 in the Control Room?

A. Any system engineer authorized by the Shift Supervisor who is performing SI system surveillances.

B. Any assistant equipment operator performing OJT on the SI system who is being monitored by the Control Room Supervisor.

C. Any individual who is in a license training program under my direct observation.

D. Any electrical maintenance supervisor troubleshooting why the SI pump vibration readings are abnormal.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 60 An Electrician has called the Control Room requesting that the RO stroke CLOSED EJ HV-8804A, RHR TRAIN 'A' TO CHARGING PUMP SUCT ISO, for MOVATS testing. A LOCAL CONTROL (LC) tag is hanging on the MCB Handswitch.

Which ONE of the following complies with APA-ZZ-00310, Workman's Protection Assurance and Caution Tagging?

A. Stroke EJ HV-8804A if the Electrician is signed on to the LC.

B. The RO must sign on to the LC in addition to the Electrician requesting the valve stroke.

C. The RO may stroke the valve after verifying the LC is on SS Hold.

D. The Electrician signed on to the LC must come to the Control Room to operate the handswitch.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 61 Per ODP-ZZ-00025, Emergency Operating Procedure Usage, in which ONE of the following cases may AFW be THROTTLED to less than 300,000 lbm/hr?

S/G NR Level Ctmt Temp Ctmt Rad A. A-30% C-24% 210°F 1 R/hr B-29% D-33%

B. A-3% C-17% 125°F 10 R/hr B-2% D-6%

C. A-17% C-18% 115°F 1 x 106 R/hr B-14% D-21%

D. A-16% C-0% 180°F 1 x 105 R/hr B-13% D-6%

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 62 Which ONE of the following plant conditions will result in the 'A' ESW Train being inoperable?

A. 'A' ESW Pump Room Supply Fan is inoperable for maintenance.

B. 'A' ESW Pump Room Unit Heater inoperable with ESW Pump Room temperature of 70°F.

C. TEF01A, 'A' Prelube Storage Tank, drained for maintenance.

D. NE01, 'A' Emergency DG, inoperable due to a governor failure.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 63 The following plant conditions exist:

Reactor has tripped due to a Loss of Off-Site Power

Pressurizer level is 20% and increasing

Pressurizer pressure is 2000 psig and increasing

CETC temperatures are 590°F and stable

RVLIS (pumps off) indicates 110%

All RCS Cold Leg temperatures are 550°F and stable Which ONE of the following describes the status of the RCS Inventory Safety Function?

A. Being maintained because cold leg temperatures are greater than 275°F.

B. Being maintained because pressurizer level is greater than 17%.

C. Not being maintained because RCS subcooling is less than 23°F subcooled.

D. Not being maintained because pressurizer level is less than program level.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 64 The following plant conditions exist:

Mode 1, 50% Reactor Power

Pzr Lev Ctrl Sel Sw, BB LS-459D is selected to L459/L460

Pzr Level channels indicate as follows:

Channel BBLT459 is 41%

Channel BBLT460 is 0%

Channel BBLT461 is 41%

Which ONE of the following actions are required to satisfy procedural requirements and Technical Specifications?

A. Switch BB LS-459D to L459/L461 and trip channel BBLT460 Pzr High Level Bistable within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. Switch BB LS-459D to L459/L461 and trip channel BBLT460 Pzr High and Low Level Bistables within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C. Switch BB LS-459D to L459/L461 and trip channel BBLT460 Pzr High Level Bistable within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; place excess letdown in service.

D. Switch BB LS-459D to L459/L461 and trip channel BBLT460 Pzr High and Low Level Bistables within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; place excess letdown in service.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 65 The following plant conditions exist:

The plant is in Mode 5.

RCS temperature is 140°F.

RCS pressure is 320 psig.

Cold Overpressure Protection Mitigation System (COMS) protection is being satisfied by the 'A' and 'B' RHR Suction Relief Valves.

It has been determined that the 'B' RHR Suction Relief Valve setpoint is set incorrectly and the relief valve is now inoperable.

Which ONE of the following actions would satisfy the Technical Specification requirement for COMS?

A. Restore the 'B' RHR Suction Relief Valve to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

B. Depressurize and vent the RCS through a vent of > 1.0 in2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

C. Align the 'A' and 'B' Pzr PORVs for COMS protection within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D. Increase all RCS cold leg temperatures to > 275°F within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 66 Which ONE of the following is the LOWEST Emergency Plan Classification at which the Emergency Response Data System (ERDS) must be activated?

A. Unusual Event B. Alert C. Site Emergency D. General Emergency

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 67 The plant is at 100% power with the following conditions:

'C' CCW pump OOS

'A' CCW Train in Service, 'B' CCW Train in Standby

NCP in Service with 120 gpm Letdown Flow The 'A' CCW pump trips due to unknown reasons.

Which ONE of the following includes required immediate actions?

A. Restart the 'A' CCW pump, if pump fails to restart, then start either 'B' or 'D' CCW pump and transfer the service loop to the 'B' CCW train.

B. Start either 'B' or 'D' CCW pump then transfer the service loop to the 'B' CCW train.

C. Trip the Reactor Coolant Pumps and the Reactor, enter E-0, Reactor Trip/Safety Injection, then transfer the service loop to the 'B' CCW train.

D. Verify 'B' CCW pump starts automatically then transfer the service loop to the 'B' CCW train.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 68 During the performance of ECA-0.0, Loss of All AC Power, battery NK11 discharge ammeter is reading 275 amps.

Which ONE of the following is the MAXIMUM time that NK01 could remain operable assuming the battery was fully charged initially?

A. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 69 The crew has implemented FR-C.1, Response to Inadequate Core Cooling.

Which ONE of the following combinations of core exit thermocouples (TC's) and indicated temperatures would require starting RCP's, even if the normally required support conditions could not be met?

of TC's Indicated Temp A. 2 2450°F B. 4 1750°F C. 6 1350 °F D. 8 750°F

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 70 Which ONE of the following could indicate a 10 gpm letdown leak between BGHV8152, CVCS Letdown System Outer CTMT Iso Valve, and the containment penetration?

A. BGPCV0131, CVCS Letdown Hx Outlet PCV, CLOSING to maintain pressure at setpoint.

B. INCREASED Component Cooling Water flow to the Letdown Heat Exchanger.

C. BGFI0132, CVCS Letdown Hx Outlet Flow Indicator, INCREASING.

D. BGTI0126, Regen Hx Charging Outlet Temperature Indicator, DECREASING.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 71 The following plant conditions exist:

NCP is running, 120 gpm letdown.

BGFT121, CVCS CHG HDR TO REGEN HX FLOW XMTR, fails.

As a result, BGFCV124 closes.

The NCP handswitch red light is lit.

BGHV8109, NCP Recirculation Valve, is open.

The following annunciators are received:

CHARGING LINE FLOW LOW

SEAL INJECTION TO RCP FLOW LOW

NCP FLOW LOW Which ONE of the following actions should be taken immediately?

A. Take manual control of BGFCV124 and open it.

B. Start a CCP and secure the NCP.

C. Open BGHV8357A or B to restore seal injection.

D. Close all letdown orifice isolation valves.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 72 A Steam Generator Tube Rupture combined with a Loss of Offsite Power has occurred.

Which ONE of the following is the PREFERRED method to INITIALLY DEPRESSURIZE the RCS?

A. Cycle Pressurizer Heaters.

B. Use Auxiliary Spray.

C. Use Normal Pressurizer Spray.

D. Use a Pressurizer PORV.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 73 The following plant conditions exist:

Rod H-8 in Control Bank "D" (CB D) was misaligned low.

Rod H-8 was withdrawn 15 steps to align it with the other rods in CB D.

The P/A converter AUTO/MAN switch was broke in the Auto position.

Which ONE of the following conditions occurs because of the P/A converter being in AUTO when rod H-8 was recovered?

A. Rod Control Non-Urgent Failure alarm when CB D rods initially moved in.

B. Rod Control Urgent Failure alarm when CB D initially moved in.

C. Rod Bank Lo alarm will be received with CB D actually above setpoint.

D. Rod Bank Lo alarm will be received with CB D actually below setpoint.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 74 The following plant conditions exist:

Mode 4 with a cooldown in progress per OTG-ZZ-00004, Plant Cooldown Hot Standby to Cold Shutdown

'B' RHR train is to be placed in a cooldown lineup per OTN-EJ-00001, Residual Heat Removal System Which ONE of the following will prevent OPENING EJ-HV-8701B, RHR Pump 'B' Suct Iso?

A. EMHV8814B, SI Pump 'B' Recirc to RWST Iso, OPEN.

B. BBPI0405, RCS Wide Range Press Xmtr, reading 306 psig.

C. EJHV8811B, CTMT Recirc Sump 'B' to RHR Pump 'B' Suct Iso, OPEN.

D. BNHV8812B, RWST to RHR Pump 'B' Suct Iso Vlv, CLOSED.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 75 The following plant conditions exist:

The unit is at 100% power with all systems aligned normally

The switchyard is in its preferred lineup with Ring Bus Breakers 52-2 and 52-3 CLOSED

A lockout occurs on 345KV Swyd Bus 'B' Which ONE of the following describes the response of the Containment Cooling Fans?

A. All fans CONTINUE to RUN in the PRESELECTED speed.

B. A & C fans are SHIFTED to SLOW speed by the shutdown sequencer.

C. B & D fans DE-ENERGIZE and are RESTARTED in FAST speed by the shutdown sequencer.

D. A & C fans DE-ENERGIZE and are RESTARTED in the PRESELECTED speed by the shutdown sequencer.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 76 The plant is in Mode 1, 100% power. An inadvertent Main Steam Line Isolation occurs resulting in a reactor trip.

Which ONE of the following correctly describes the steam generator response? (Assume no operator action.)

A. Rapid pressure increase causes steam generator levels to increase, steam generator PORVs and Safety Valves lift relieving the pressure, steam generator levels decrease and main feedwater level control increases feed to regain level.

B. Rapid pressure increase causes steam generator levels to increase, steam generator PORVs lift relieving the pressure, steam generator levels decrease and auxiliary feedwater will feed to regain level.

C. Rapid pressure increase causes steam generator levels to decrease, steam generator PORVs and Safety Valves lift to relieve the pressure, steam generator levels decrease and auxiliary feedwater will feed to regain level.

D. Rapid pressure increase causes steam generator levels to decrease, steam generator PORVs lift relieving the pressure, steam generator levels decrease and main feedwater level control increases feed to regain level.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 77 The reactor tripped 5 minutes ago.

Which ONE of the following completes the statement concerning the heat transfer relationship between the RCS and Steam Generators?

The heat transfer rate between the RCS and the S/Gs will:

A. decrease as RCS temperature increases and AFW flow increases.

B. decrease as AFW temperature decreases and AFW flow increases.

C. increase as AFW temperature increases and RCS flow decreases.

D. increase as RCS temperature increases and AFW flow increases.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 78 Which ONE of the following combinations of Borated Water Volume, Boron Concentration, and Solution Temperature would meet the Technical Specification LCO for the RWST in Mode 4?

Borated Water Volume Boron Concentration Solution Temperature A. 395,000 gal 2325 ppm 65°F B. 350,000 gal 2385 ppm 85°F C. 400,000 gal 2415 ppm 95°F D. 412,000 gal 2450 ppm 105°F

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 79 The following plant conditions exist:

Compressor Sequencer Selector Switch, KAHS0043, is selected to the CAB position.

All three air compressors are selected to AUTOMATIC.

'A' Air Compressor (CKA01A) is running unloaded.

'B' Air Compressor (CKA01B) is not running.

'C' Air Compressor (CKA01C) is running loaded.

KA-PV-11, Service Air Isolation Valve is open.

Which ONE of the following describes the correct system response to an air leak that results in air system pressure decreasing to 105 psig?

A. Only CKA01A and CKA01C are running and both are loaded.

B. All three air compressors are running, but only two are loaded.

C. Only CKA01A and CKA01C are running and both are loaded, KA-PV-11 is closed.

D. All three air compressors are running and all three are loaded, KA-PV-11 is closed.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 80 The following plant conditions exist:

A Rx Startup is in progress following a mid-cycle outage

Rx power has been stabilized at 1E-8 amps

RCS temperature is at the no-load value

Critical data has been taken

Prior to any additional control rod movement, a single S/G Safety Valve on SG 'D' fails open and remains open

RCS Tavg decreases 9°F and reactor power starts to increase Which ONE of the following states the most restrictive action required to satisfy Technical Specification LCO(s)?

A. Reduce power range high flux reactor trip setpoints to < 85% rated thermal power.

B. Restore the inoperable S/G safety valve to operable status prior to entering Mode 1.

C. Restore Tavg or be in Mode 2 with Keff < 1.0 and all RCS TCold > 500°F within 30 min.

D. Immediately initiate emergency boration to restore adequate Shutdown Margin.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 81 The following plant conditions exist:

Reactor power is 45%

Control Rod Deviation alarm is lit

Rod at Bottom alarm is lit

Two/More Rods at Bottom alarm is lit

Power Range Channel Deviation alarm is lit

Rod Bottom LEDs are lit for Shutdown Bank 'A' Rods P4 and D2 Which ONE of the following describes an applicable Technical Specification and the required procedure response to these conditions?

A. T/S 3.2.4, Quadrant Power Tilt Ration, is applicable and procedures require that the axial flux difference and quadrant power tilt ratio be checked.

B. T/S 3.1.4, Rod Group Alignment Limits, is applicable and procedures require you to trip the reactor and perform E-0, Reactor Trip or Safety Injection.

C. T/S 3.1.4, Rod Group Alignment Limits, is applicable and up to two rods are allowed to be restored per OTO-SF-00004, Misalignment of Control Rods.

D. T/S 3.1.5, Shutdown Bank Insertion Limits, is applicable and procedures require you to recover the dropped control rods per OTO-SF-00003, Dropped Control Rod.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 82 Which ONE of the following conditions would VIOLATE Technical Specification requirements for Containment Building Penetrations?

A. Both Containment Personnel Air Lock doors are OPEN with core offload in progress.

Administrative controls are in place to ensure that one door is capable of being CLOSED.

B. Additional ventilation for personnel in Containment is being provided through the Emergency Air Lock via temporary blowers while draining the Refueling Pool following core offload.

C. Performing Control Rod Drag testing following core reload while scaffolding is being REMOVED from Containment via the Equipment Hatch.

D. Performing valve lineups to DRAIN the secondary side of all four steam generators with the RCS Tavg at 185°F.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 83 The following plant conditions exist:

Large Break LOCA in progress

Crew is performing FR-Z.1, Response To High Containment Pressure, due to an ORANGE path on Containment Pressure

CTMT Pressure is 31 psig and INCREASING

Annunciator 47C, RWST LEV LOLO 1 AUTO XFR, has just ACTUATED Which ONE of the following should be performed?

A. CONTINUE in FR-Z.1, when completed, transition to ES-1.3, Transfer To Cold Leg Recirculation. Upon completion transition to E-1, Loss of Reactor or Secondary Coolant.

B. CONTINUE in FR-Z.1 until Containment Pressure is LESS THAN 25 psig, then transition to ES-1.3, Transfer to Cold Leg Recirculation.

C. SUSPEND performance of FR-Z.1, transition to ES-1.3, Transfer To Cold Leg Recirculation. Upon completion return to FR-Z.1.

D. SUSPEND performance of FR-Z.1, transition to ES-1.3, Transfer To Cold Leg Recirculation. Complete ES-1.3 through Step 3, then return to FR-Z.1.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 84 The following plant conditions exist:

Mode 2, Reactor Power is 3%

RCS Loop 1 RTD Channel has failed and all associated bistables have been tripped

Sometime later in the shift, Power Range NI Channel N44 fails high (bistables have NOT been tripped)

Which ONE of the following statements describes the appropriate action to be taken?

A. Continue the startup. T/S 3.3.1 allows the startup to continue as long as the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. Enter T/S 3.0.3 and begin a unit shutdown per OTG-ZZ-00005, Plant Shutdown 25%

Power to Hot Standby.

C. Trip the reactor and enter procedure E-0, Reactor Trip or Safety Injection.

D. Hold the startup. T/S 3.3.1 prevents entry into Mode 1 until N44 is operable.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 85 The following plant conditions exist:

The plant was operating at 4% reactor power

Both trains of Essential Service Water (ESW) were determined to be inoperable

The operators placed the plant in HOT STANDBY exactly 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after determining that the second ESW train was inoperable Which ONE of the following time limits apply to placing the plant in HOT SHUTDOWN and then COLD SHUTDOWN?

A. HOT SHUTDOWN must be achieved within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of reaching HOT STANDBY and COLD SHUTDOWN must be achieved within an additional 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

B. HOT SHUTDOWN must be achieved within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of reaching HOT STANDBY and COLD SHUTDOWN must be achieved within an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C. HOT SHUTDOWN must be achieved within 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of reaching HOT STANDBY and COLD SHUTDOWN must be achieved within an additional 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

D. HOT SHUTDOWN must be achieved within 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of reaching HOT STANDBY and COLD SHUTDOWN must be achieved within an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 86 Technical Specifications require all full-length control rods to be OPERABLE in Modes 1 and 2 (with special test exceptions).

Which ONE of the following would cause a control rod to be INOPERABLE?

A. The CRDM stationary gripper coil turns OFF after the movable gripper coil turns ON during rod withdrawal.

B. The CRDM lift coil turns ON while the movable gripper coil is ON during rod withdrawal.

C. The CRDM lift coil turns ON and then the movable gripper coil turns ON during rod insertion.

D. The CRDM stationary gripper coil turns OFF before the movable gripper coil turns ON during rod insertion.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 87 The plant is in Mode 2 at 3% Reactor Power, commencing warm-up of the main turbine.

Which ONE of the following could be a direct result of a loss of Vital AC Instrument Bus NN02?

A. Intermediate Range High Flux Reactor Trip.

B. Source Range High Flux Reactor Trip.

C. Charging Pump Suction Swaps to the RWST.

D. Idle Component Cooling Water Pump Start.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 88 A Pressurizer Pressure instrument has failed low. All immediate and subsequent operator actions have been completed for the failed instrument per OTO-BB-00006, Pressurizer Pressure Channel Failure.

Which ONE of the following remains INACCURATE despite the fact that the alternate instruments have been selected?

(Assume NO actions have been performed by I&C personnel.)

A. Pressurizer Pressure Control B. Pressurizer Pressure Recorder C. OPT/OTT Temp Recorder D. Core Subcooling Monitor

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 89 The plant was initially in Mode 1. The following plant conditions now exist:

A large break LOCA has occurred inside Containment

Only the 'B' Train of Safety Injection AUTOMATICALLY ACTUATED

Train 'A' ECCS components have been STARTED/OPERATED MANUALLY

RWST level is 35% and DECREASING

'B' Train RHR Ctmt Recirc Sump Suction Valve, EJ HV-8811B, is OPEN

'A' Train RHR Ctmt Recirc Sump Suction Valve, EJ HV-8811A, is CLOSED Which ONE of the following describes why the 'A' RHR Pump must be temporarily STOPPED to complete the switchover to the Cold Leg Recirculation mode of ECCS?

A. RHR System Hot Leg Recirculation Valve, EJ HV-8716A, must be CLOSED in order to OPEN RHR Ctmt Recirculation Sump Suction Valve, EJ HV-8811A.

B. RWST to RHR Pump Suction Valve, BN HV-8812A, must be CLOSED in order to OPEN Ctmt Recirculation Sump Suction Valve, EJ HV-8811A.

C. RWST to RHR Pump Suction Valve, BN HV-8812A, must be CLOSED in order to OPEN RHR to Charging Pump Valve, EJ HV-8804A.

D. RHR to Accumulator Injection Valve, EJ HV-8809A, must be CLOSED in order to OPEN RHR Ctmt Recirculation Sump Suction Valve, EJ HV-8811A.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 90 The following plant conditions exist:

Mode 1, 100% Reactor Power

RCS specific activity is 50 microcuries/gm DOSE EQUIVALENT I-131 Which ONE of the following is the Chemistry sampling requirements per OTO-BB-00005, Reactor Coolant System High Activity?

A. Normal 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sample requirements are necessary.

B. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until activity decreases for 3 consecutive samples.

C. As directed by the On-Shift Chemistry Supervisor.

D. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months until activity decreases to less than 1 microcurie/gm.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 91 The following plant conditions exist:

The plant is in Mode 5

Midloop operations are in progress

SG hot and cold leg manway covers are removed

SG nozzle dams are installed in the hot legs

SG nozzle dams are NOT installed on the cold legs

Loss of RHR cooling occurs Which ONE of the following could occur as a result of this event?

A. Steam formation in the hot leg will cause an erroneously low RCS Loop Level indication.

B. Steam formation in the reactor vessel head will displace water from the reactor vessel and force water out the cold leg manways.

C. Steam formation in the reactor vessel head will increase RCS pressure and blow out the hot leg nozzle dams.

D. Steam formation in the hot leg will ultimately collapse, resulting in severe water hammer.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 92 The plant is in Mode 1 at 75% reactor power.

Which ONE of the following is a correct IMMEDIATE ACTION for a main feed pump trip under these conditions per OTO-AE-00001, Feedwater System Malfunction?

A. Manually trip the reactor and enter E-0, Reactor Trip or Safety Injection.

B. Quickly run back turbine generator load to less than 60% or 750 MWe.

C. Use normal boration/adjust turbine load as necessary to match Tave and Tref.

D. Restore steam generator level to the program level of 50%.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 93 The Callaway Plant is operating at 30% power and it is necessary to secure the 'B' Reactor Coolant Pump due to high vibration. After the RCP is tripped, the 'B' Loop T

_________________ and the other Loop Ts _________________. (Assume unit load is held constant.)

A. Increases, Decrease B. Increases; Increase C. Decreases; Decrease D. Decreases; Increase

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 94 The plant is initially operating at 100%. A large Steam Line Rupture in Containment has resulted in the following:

CTMT Temperature is 180°F

CTMT Pressure is 8 psig Which ONE of the following describes the response of the Containment Coolers?

A. 'A' Containment Cooler supplies the Instrument Tunnel in FAST speed.

B. 'B' Containment Cooler supplies the Pressurizer Enclosure Compartment in SLOW speed.

C. 'C' Containment Cooler flows DIRECTLY to the containment atmosphere in SLOW speed.

D. 'D' Containment Cooler flows DIRECTLY to the containment atmosphere in FAST speed.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 95 A liquid radwaste release from Discharge Monitor Tank 'A' is in progress.

Which ONE of the following conditions would AUTOMATICALLY terminate the release?

A. Cooling tower blowdown flow rate is REDUCED to 6000 gpm.

B. RW bldg discharge rad monitor, HB RE-18, FAILS resulting in a Hi Hi alarm.

C. Steam generator blowdown surge tank level INCREASES to the Hi Hi setpoint.

D. A Hi Hi alarm on S/G blowdown discharge rad monitor causes BM FV-54 to CLOSE.

AUGUST 2002 NRC SRO WRITTEN EXAM QUESTION: 96 Which ONE of the following correctly identifies the parameters and values used by an operator to ensure the temperature difference between the PZR and the Spray Fluid are within the specified limit(s) in the Technical Specifications when initiating PZR Spray?