ML17165A558

302 Draft SRO Written Exam

ML17165A558
Person / Time
Site:	Oconee
Issue date:	06/28/2017
From:	Division of Reactor Safety II
To:
References
Download: ML17165A558 (104)

Text

Oconee Nuclear Station Question: 1 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 2 conditions:

Initial conditions:

Time = 1200:00 Reactor power = 100%

Both MFDW Pumps tripped RCS Pressure is peaking at 2475 psig 1RC-66 (PORV) is OPEN Current conditions:

Time = 1200:30 RCS Pressure= 2135 psig decreasing 1RC-66 OPEN Core SCM = 18°F decreasing

1) In accordance with Rule 2 (Loss of SCM), all RCPs must be secured if __(1)__

SCM(s) reach(s) zero.

2) A reason RCPs are secured per the above requirement is to __(2)__.

Which ONE of the following completes the statements above?

A. 1. ANY

2. prevent pump damage that occurs from pumping a steam/water mixture B. 1. ANY

2. ensure RCPs are secured before the RCS can evolve to a void fraction of >

70%

C. 1. core ONLY

2. prevent pump damage that occurs from pumping a steam/water mixture D. 1. core ONLY

2. ensure RCPs are secured before the RCS can evolve to a void fraction of >

70%

Page 1 of 100

Oconee Nuclear Station Question: 2 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor Power = 100%

RCS Pressure = 2100 psig decreasing RBNS level increasing Reactor Building RIAs are in alarm

1) In accordance with Rule 2 (Loss of SCM), ANY RCP that remains running two minutes after its operating limit is reached is __(1)__.

2) If ANY RCP cannot be secured by the associated RCP Breaker switch on 1UB2, Rule 2 directs de-energizing __(2)__ 6900KV bus(es).

Which ONE of the following completes the statements above?

A. 1. left running

2. ONLY the associated B. 1. left running

2. BOTH C. 1. secured ONLY if its amps are stable

2. ONLY the associated D. 1. secured ONLY if its amps are stable

2. BOTH Page 2 of 100

Oconee Nuclear Station Question: 3 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Time = 0400 Reactor Power = 100%

RCS pressure 2100 psig rapidly decreasing RB Pressure 0.3 psig rapidly increasing Multiple RB RIA alarms Current conditions:

Time = 0402:30 RCS pressure = 104 psig slowly decreasing RB pressure = 16.2 psig slowly increasing Which ONE of the following describes the lights that will be ILLUMINATED in the picture below?

A. Damper RED light and RBCU GREEN light B. Damper RED light and RBCU AMBER light C. Damper GREEN light and RBCU GREEN light D. Damper GREEN light and RBCU RED light Page 3 of 100

Oconee Nuclear Station Question: 4 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 80%

1A Feedwater Flow = 4.4 x 106 LB/HR 1B Feedwater Flow = 4.4 x 106 LB/HR Current conditions:

1B1 RCP trips

1) Reactor power will AUTOMATICALLY be reduced to a MAXIMUM of __ (1) __%

Core Thermal Power.

2) When the MAXIMUM power level is reached, a MFDW flow of __ (2) __106 LB/HR will be established to the 1A Steam Generator.

Which ONE of the following completes the statements above?

A. 1. 65

2. 5.4 B. 1. 74

2. 5.4 C. 1. 65

2. 6.1 D. 1. 74

2. 6.1 Page 4 of 100

Oconee Nuclear Station Question: 5 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Time = 1200 Reactor power = 100%

1HP-31 failed CLOSED AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection) initiated Current conditions:

Time = 1300 1HP-31 has been repaired Seal injection flow is being re-established to the RCP seals

1) In accordance with AP/14, at Time = 1200 all four RCPs __(1)__.

2) RCP seal injection flow is re-established slowly to prevent thermal shock and possible damage to the RCP __ (1) __.

Which ONE of the following completes the statements above?

A. 1. must be secured

2. seals B. 1. must be secured

2. thermal barrier C. 1. can continue to operate

2. seals D. 1. can continue to operate

2. thermal barrier Page 5 of 100

Oconee Nuclear Station Question: 6 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 2 conditions:

RCS cooldown in progress LPI aligned in the Series Mode

1) The reason Series Mode was developed for Unit 2 was to provide __(1)__.

2) A loss of the __(2)__ LPI Pumps would result in a total loss of Decay Heat Removal.

A. 1. a backup to the Switchover mode of LPI

2. 2A and 2C B. 1. a backup to the Switchover mode of LPI

2. 2B and 2C C. 1. additional cooling capacity during 2/0 pump ops

2. 2A and 2C D. 1. additional cooling capacity during 2/0 pump ops

2. 2B and 2C Page 6 of 100

Oconee Nuclear Station Question: 7 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

Initial conditions:

Time = 1200 Reactor power = 100%

3A CC pump trips 3B CC pump fails to start Current conditions:

Time = 1203 3HP-5 has closed 3B CC pump has been manually started Pressurizer level = 235 increasing Which ONE of the following states the:

1) Letdown temperature setpoint that resulted in 3HP-5 closing?

2) MINIMUM indicated Pressurizer level that will require declaring Tech Spec 3.4.9 (Pressurizer) LCO NOT met in accordance with PT/3/A/0600/001 (Periodic Instrument Surveillance)?

A. 1. 130°F

2. 260 inches B. 1. 135°F

2. 260 inches C. 1. 130°F

2. 285 inches D. 1. 135°F

2. 285 inches Page 7 of 100

Oconee Nuclear Station Question: 8 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 90%

1B MFDW pump trips Current conditions:

Reactor power = 62% stable RCS pressure = 2185 psig slowly decreasing Pressurizer level = 229 inches slowly decreasing Pressurizer temperature = 648°F slowly increasing Pressurizer Heater Bank 1 switch is ON Pressurizer Heater Bank 2 (Groups B & D) are in AUTO and off Pressurizer Heater Banks 3 and 4 are in AUTO and off

1) The pressurizer is __ (1) __.

2) The pressurizer saturation circuit __ (2) __ responding as expected.

Which ONE of the following completes the statements above?

A. 1. subcooled

2. is B. 1. subcooled

2. is NOT C. 1. saturated

2. is D. 1. saturated

2. is NOT Page 8 of 100

Oconee Nuclear Station Question: 9 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

BOTH MFDW pumps trip Current conditions:

Reactor power = 57% slowly decreasing

1) In accordance with Rule 1 (ATWS), the CRD breakers are opened __(1)__ aligning HPI injection from the BWST.

2) The direction given to the operator opening the CRD breaker is to __(2)__ Arc Flash PPE.

Which ONE of the following completes the statements above?

A. 1. prior to

2. wear B. 1. prior to

2. NOT wear C. 1. after

2. wear D. 1. after

2. NOT wear Page 9 of 100

Oconee Nuclear Station Question: 10 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Loss of Heat Transfer has occurred Unit 1 TDEFWP is now available to feed the Steam Generators 1A SG level = 8 slowly decreasing 1A SG pressure = 412 psig slowly decreasing 1B SG level = 5 slowly decreasing 1B SG pressure = 385 psig slowly decreasing In accordance with Rule 7 (Steam Generator Feed Control), the MAXIMUM initial feed rate allowed to EACH Steam Generators is limited to __(1)__ gpm in order to prevent

__(2)__.

Which ONE of the following completes the statement above?

A. 1. 100

2. damage to the Steam Generators B. 1. 100

2. an RCS overcooling event C. 1. 50

2. damage to the Steam Generators D. 1. 50

2. an RCS overcooling event Page 10 of 100

Oconee Nuclear Station Question: 11 ILT46 ONS SRO NRC Examination (1 point)

Oconee plant conditions:

Station blackout has occurred The EOP Blackout tab has been in progress for three hours 1CA voltage = 104 VDC Which ONE of the following describes why the Blackout tab directs the crew to FAIL 1CC-8 (CC RETURN PENT (54) OUTSIDE BLOCK) closed?

A. 1CC-8 will fail open if IA pressure decreases to < 35 psig.

B. Prevents auto restart of CC pumps once AC power is restored.

C. Prevents cooler damage from an open flowpath to coolers when flow is restored.

D. 1CC-8 will fail open when DC power is lost to the solenoid.

Page 11 of 100

Oconee Nuclear Station Question: 12 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor trip from 100% power due to a loss of offsite power (Switchyard Isolation)

CT-1 lockout Current conditions:

AP/11 (Recovery from Loss of Power) initiated S11 (STBY BUS 1 to MFB1) Breaker will NOT close LOAD SHED COMPLETE is NOT lit on the ES Component Status Panel In accordance with AP/11, electrical loads are secured to _______.

Which ONE of the following completes the statement above?

A. prevent exceeding CT-4 Overload Limits B. prevent exceeding CT-5 Overload Limits C. ensure S12 (STBY BUS 2 to MFB2) Breaker is operated within limits D. ensure adequate voltage to ES equipment during a subsequent LOCA Page 12 of 100

Oconee Nuclear Station Question: 13 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Large Break LOCA occurred 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago RCS Pressure = 30 psig 1A & 1B LPI Pumps are running Current conditions:

1KVIA is de-energized 1SA-18/A-3 RVLIS/ICCM/RG1.97 Train A Trouble actuated Which ONE of the following describes:

1) the impact on the LPI system instrumentation?

2) what alternate indication can be used to determine the status of the LPI pumps?

A. 1. LPI HDR 1A INJ FLOW (gpm) is blank

2. 1A LPI Pump amps and breaker indicating lights B. 1. LPI HDR 1A INJ FLOW (gpm) is blank

2. 1A LPI HDR flow computer point (OAC)

C. 1. LPI HDR 1B INJ FLOW (gpm) is blank

2. 1B LPI Pump amps and breaker indicating lights D. 1. LPI HDR 1B INJ FLOW (gpm) is blank

2. 1B LPI HDR flow computer point (OAC)

Page 13 of 100

Oconee Nuclear Station Question: 14 ILT46 ONS SRO NRC Examination (1 point)

Given the following plant conditions:

KHU-1 generating to grid 1DA input breaker (K1-DA-1A, Batt #1 Ckt Bkr) fails OPEN 2SA-17/A3 (Unit 1 Alarm Lockout) actuates

1) KHU #1 __(1)__ trip.

2) The reason DC power is used for Keowee control power is that it will be available for a MINIMUM of approximately __ (2) __ hour(s) following a loss of ALL AC power.

Which ONE of the following completes the statements above?

A. 1. will NOT

2. one B. 1. will NOT

2. four C. 1. will

2. one D. 1. will

2. four Page 14 of 100

Oconee Nuclear Station Question: 15 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor Power = 100%

AP/22 (Loss of Instrument Air) in progress

1) The MINIMUM condition(s) that will result in a loss of control of 1HP-31 is a loss of

__(1)__.

2) Once the above condition(s) are met, the operator sent to operate 1HP-31 manually will INITIALLY be required to throttle 1HP-31 in the __(2)__ direction.

Which ONE of the following completes the statements above?

A. 1. IA pressure ONLY

2. closed B. 1. IA pressure ONLY

2. open C. 1. IA AND AIA pressure

2. closed D. 1. IA AND AIA pressure

2. open Page 15 of 100

Oconee Nuclear Station Question: 16 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

A loss of ALL sources of Steam Generator feed has occurred HPI Forced Cooling in progress RCS pressure = 2210 psig slowly decreasing Pzr Level = 380 inches increasing Core SCM = 56°F increasing In accordance with Rule 6 (HPI), HPI flow __(1)__ be throttled because __(2)__.

Which ONE of the following completes the statement above?

A. 1. may NOT

2. RCS pressure is decreasing B. 1. may NOT

2. CETCs are increasing C. 1. may

2. Pzr Level is increasing D. 1. may

2. CETCs are decreasing Page 16 of 100

Oconee Nuclear Station Question: 17 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

1A Main Steam Line Break occurs Current conditions:

Reactor has tripped RCS Tave = 544°F slowly increasing 1A SG Pressure = 0 psig 1B SG Pressure = 990 psig slowly increasing Turbine bypass valves in Auto Reactor Building pressure = 0.2 psig stable Which ONE of the following describes:

1) the status of the TDEFWP?

2) how subsequent operation of the TDEFWP would be performed?

A. 1. Operating

2. Can be secured with TDEFWP control switch before AFIS is reset B. 1. Operating

2. Can be secured with TDEFWP control switch ONLY after AFIS is reset C. 1. NOT operating

2. Can be started with TDEFWP control switch before AFIS is reset D. 1. NOT operating

2. Can be started with TDEFWP control switch ONLY after AFIS is reset Page 17 of 100

Oconee Nuclear Station Question: 18 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor tripped from 100% power 1MS-10 (Main Steam Relief Valve) is stuck open Main Steam pressure is being reduced in an attempt to reseat 1MS-10 In accordance with Subsequent Actions of the EOP,

1) Main Steam pressure will be reduced in __(1)__ psig increments.

2) the MINIMUM RCS temperature allowed while reseating a MSRV without running a shutdown margin calculation is __(2)__ °F.

Which ONE of the following completes the statements above?

A. 1. 10

2. 532 B. 1. 20

2. 532 C. 1. 10

2. 525 D. 1. 20

2. 525 Page 18 of 100

Oconee Nuclear Station Question: 19 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor Power = 98% decreasing Control Rod 4 in Group 6 = 0% withdrawn

1) ICS will automatically reduce Reactor power to __(1)__% Core Thermal Power.

2) The basis for decreasing reactor power to the above level is to ensure __(2)__.

Which ONE of the following completes the statements above?

A. 1. 65

2. Local Linear Heat Rate limits are not exceeded B. 1. 65

2. adequate margin in preparation for resetting RPS trip set points C. 1. 55

2. Local Linear Heat Rate limits are not exceeded D. 1. 55

2. adequate margin in preparation for resetting RPS trip set points Page 19 of 100

Oconee Nuclear Station Question: 20 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor in MODE 5 1DIC inverter DC Input breaker trips Source Range 1NI-2 will be restored __(1)__.

Which ONE of the following completes the statement above?

A. manually by placing the Manual bypass switch to the Inverter Output position B. manually by placing the Manual bypass switch to the AC Line position C. automatically by way of the ASCO transfer switch D. automatically by way of the Static Transfer Switch Page 20 of 100

Oconee Nuclear Station Question: 21 ILT46 ONS SRO NRC Examination (1 point)

Which ONE of the following is the condenser vacuum (inches Hg) SETPOINT stated in AP/27 (loss of condenser vacuum) that will require manually tripping the Reactor when in MODE 1?

A. 25 B. 22 C. 21.75 D. 19 Page 21 of 100

Oconee Nuclear Station Question: 22 ILT46 ONS SRO NRC Examination (1 point) 1RIA-3, (Refueling Canal Wall Area Monitor),

1) HIGH alarm __(1)__ cause a Reactor Building Evacuation alarm.

2) is NOT in HIGH alarm during Power Operations because the __(2)__.

Which ONE of the following completes the statements above?

A. 1. will

2. setpoint is raised to provide for indication of RCS leakage B. 1. will

2. detector is removed from the Reactor Building C. 1. will NOT

2. setpoint is raised to provide for indication of RCS leakage D. 1. will NOT

2. detector is removed from the Reactor Building Page 22 of 100

Oconee Nuclear Station Question: 23 ILT46 ONS SRO NRC Examination (1 point)

Given the following plant conditions:

An Active Fire is taking place in Unit 2 Equipment Room The SRO dispatches you to the Unit 1 Equipment Room to determine Control Room Ventilation and Fire Damper positions

1) Control Room Ventilation system damper positions __(1)__ be determined by observing the linkage pointing to either the OPEN or CLOSED tag.

2) Observing that all damper blades are aligned in either the open or closed position

__(2)__ the ONLY way to determine Fire Damper positions between Unit 1 and Unit 2 Equipment Rooms.

Which ONE of the following completes the statements above?

A. 1. can

2. is B. 1. can

2. is NOT C. 1. can NOT

2. is D. 1. can NOT

2. is NOT Page 23 of 100

Oconee Nuclear Station Question: 24 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 2 conditions:

Initial conditions:

Reactor power = 90%

Loop A Controlling Thot fails HIGH 2SA2/B4 (RC AVERAGE TEMP HIGH/LOW) actuated Current conditions:

The Diamond and BOTH FDW Masters taken to HAND Which ONE of the following describes the INITIAL action taken by an RO, and the reason for the action, in accordance with OMP 1-18 (Implementation Standard During Abnormal And Emergency Events)?

A. Decrease Feedwater to stabilize reactor power B. Decrease Feedwater to stabilize RCS pressure C. Insert control rods to stabilize RCS pressure D. Insert control rods to stabilize reactor power Page 24 of 100

Oconee Nuclear Station Question: 25 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 2 conditions:

Reactor power = 100%

2SA-18/A-11, TURBINE BSMT WATER EMERGENCY HIGH LEVEL, is in alarm Turbine Building flooding is confirmed In accordance with the Turbine Building Flood tab of the EOP

1) Emergency Feedwater pumps ___(1)___ required to be utilized to fill the Steam Generators in addition to the Main Feedwater pumps.

2) While maximizing feed to the SGs, the MAXIMUM feed rate limits of Rule 7 (SG Feed Control) ___(2)____ apply while maintaining Tave > 532 °F.

Which ONE of the following completes the statements above?

A. 1. are

2. do B. 1. are

2. do NOT C. 1. are NOT

2. do D. 1. are NOT

2. do NOT Page 25 of 100

Oconee Nuclear Station Question: 26 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 1200 Reactor trips from 100% power due to a 1A Main Steam Line Break BOTH 1A and 1B SG pressures rapidly decreasing Core SCM = 0ºF Time = 1204 Tcold reaches lowest value of 416ºF Time = 1215 Tcold = 498ºF stable Core SCM = 78ºF stable Rule 2 (Loss of SCM) is complete

1) __ (1) __ was the EOP tab that was entered first from Subsequent Actions.

2) Rule 8 (Pressurized Thermal Shock) __ (2) __ required to be invoked.

Which ONE of the following completes the statements above?

A. 1. Loss of SCM

2. is B. 1. Loss of SCM

2. is NOT C. 1. Excessive Heat Transfer

2. is D. 1. Excessive Heat Transfer

2. is NOT Page 26 of 100

Oconee Nuclear Station Question: 27 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 2 conditions:

Initial conditions:

Main Steam Line Break occurred on the 2A SG outside of containment The Excessive Heat Transfer tab of the EOP was completed The crew transitioned to the Forced Cooldown (FCD) Tab Current conditions:

ALL RCPs are OFF The decision has been made to perform a natural circulation cooldown

1) In accordance with Rule 7 (SG Feed Control), level in the 2B SG is required to be maintained at __(1)___ while performing the cooldown.

2) In accordance with the FCD tab, the first action taken to collapse a bubble formed in the Reactor Vessel head during the cooldown is to __(2)___.

Which ONE of the following completes the statements above?

A. 1. 240 XSUR

2. open the head vents B. 1. 240 XSUR

2. increase RCS pressure C. 1. 270 XSUR

2. open the head vents D. 1. 270 XSUR

2. increase RCS pressure Page 27 of 100

Oconee Nuclear Station Question: 28 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 1200 Reactor power = 60% stable Delta Tc ICS station in HAND 1A1 RCP trips At Time = 1230, 1A Steam Generator Level will be __(1)__ at Time = 1200 because

__(2)__.

Which ONE of the following completes the statement above?

ASSUME NO OPERATOR ACTIONS A. 1. lower than

2. ICS will runback power to 55%

B. 1. lower than

2. Feedwater flows will re-ratio based on the RCS loop flow mismatch C. 1. approximately the same as

2. Feedwater re-ratio is blocked with delta Tc in HAND D. 1. approximately the same as

2. the re-ratio will make 1A SG level increase but the power reduction will then reduce it to approximately its original value Page 28 of 100

Oconee Nuclear Station Question: 29 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

1A1 RCP start in progress AC oil lift pump is started Current conditions:

Oil lift pump low discharge pressure does NOT clear

1) The AC oil lift pump __ (1) __.

2) The bypass position on the RCP start/stop switch __ (2) __ bypass ALL RCP starting interlocks.

Which ONE of the following completes the statements above?

A. 1. must be manually stopped

2. will NOT B. 1. must be manually stopped

2. will C. 1. will automatically stop after a time delay

2. will NOT D. 1. will automatically stop after a time delay

2. will Page 29 of 100

Oconee Nuclear Station Question: 30 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

Reactor Power = 100%

3A Purification IX was taken out of service 6 months ago 3A Purification IX was just placed back in service without being saturated to current RCS boron concentration

1) Group 7 control rods will be __(1)__ .

2) Available shutdown margin (SDM) will be __(2)__.

Which ONE of the following completes the statements above?

A. 1. inserting

2. increasing B. 1. inserting

2. decreasing C. 1. withdrawing

2. increasing D. 1. withdrawing

2. decreasing Page 30 of 100

Oconee Nuclear Station Question: 31 ILT46 ONS SRO NRC Examination (1 point)

Which ONE of the following consists of ONLY components powered from 2TD?

A. 2C LPI pump and 2B HPI pump B. 2C LPI pump and 2C HPI pump C. 2B LPI pump and 2B HPI pump D. 2B LPI pump and 2C HPI pump Page 31 of 100

Oconee Nuclear Station Question: 32 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

Reactor power = 100%

"3A" Core Flood Tank o Pressure = 587 psig stable o Level = 12.87 ft stable "3B" Core Flood Tank o Pressure = 629 psig stable o Level = 13.36 ft stable Which ONE of the following describes the potential adverse effects and its cause that could occur during a large break LOCA?

A. 3A CFT will discharge an inadequate volume of water into the core due to the CFT level.

B. 3A CFT will discharge an inadequate volume of water into the core due to the CFT pressure.

C. 3B CFT will discharge too much inventory during the blow down phase and not cover the hotspot during re-flood due to CFT level.

D. 3B CFT will discharge too much inventory during the blow down phase and not cover the hotspot during re-flood due to CFT pressure.

Page 32 of 100

Oconee Nuclear Station Question: 33 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Large Break LOCA has occurred In accordance with EOP Encl. 5.12, which ONE of the following describes:

1) the range of BWST levels (ft) where LPI pump suction would be aligned to both the RB Emergency Sump and the BWST simultaneously?

2) the action(s) that would be required if 1LP-22 failed to close when isolating the BWST?

A. 1. 15 - 9

2. stop the 1B LPI pump AND 1B RBS pump B. 1. 15 - 9

2. Maximize total LPI flow < 3100 gpm C. 1. 9 - 6

2. stop the 1B LPI pump AND 1B RBS pump D. 1. 9 - 6

2. Maximize total LPI flow < 3100 gpm Page 33 of 100

Oconee Nuclear Station Question: 34 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor in MODE 1 Quench Tank is being pumped to 1A BHUT using the Quench Tank Pump AND the Component Drain Pump

1) In accordance with OP/1/A/1104/017 (Quench Tank Operations), Quench Tank Level shall be maintained at a MAXIMUM of __(1)__ inches.

2) The __(2)__ will automatically trip once Quench Tank level reaches 80 inches Which ONE of the following completes the statements above?

A. 1. 90

2. Quench Tank Pump ONLY B. 1. 90

2. Quench Tank Pump AND Component Drain Pump C. 1. 100

2. Quench Tank Pump ONLY D. 1. 100

2. Quench Tank Pump AND Component Drain Pump Page 34 of 100

Oconee Nuclear Station Question: 35 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

1A and 1B Letdown Coolers in service Letdown flow = 78 gpm Current conditions:

1A Letdown Cooler is removed from service by the RO in the Control Room

1) CC flow to the 1B Letdown Cooler will __ (1) __.

2) In accordance with OP/1/A/1104/002 (HPI System), once the 1A Letdown Cooler is isolated the MAXIMUM letdown flow is __(2)__ gpm.

Which ONE of the following completes the statements above?

A. 1. stay the same

2. 88 B. 1. stay the same

2. 125 C. 1. increase

2. 88 D. 1. increase

2. 125 Page 35 of 100

Oconee Nuclear Station Question: 36 ILT46 ONS SRO NRC Examination (1 point)

Which ONE of the following sets of components are BOTH cooled by the Component Cooling system.

A. RCP Seal Return Coolers AND Quench Tank Coolers B. RCP Seal Return Coolers AND RCP Motor Coolers C. RCP Seal Coolers AND Quench Tank Coolers D. RCP Seal Coolers AND RCP Motor Coolers Page 36 of 100

Oconee Nuclear Station Question: 37 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

Time = 1200 Reactor power = 100%

Channel A AND Channel B narrow range RCS pressure fail HIGH

1) At Time = 1200 an AUTOMATIC reactor trip __(1)__ occur.

2) At Time = 1205 an AUTOMATIC ES actuation __(2)__ have occurred.

Which ONE of the following completes the statements above?

ASSUME NO OPERATOR ACTIONS A. 1. will

2. will B. 1. will

2. will NOT C. 1. will NOT

2. will D. 1. will NOT

2. will NOT Page 37 of 100

Oconee Nuclear Station Question: 38 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

1B1 Reactor coolant pump trips Which ONE of the following RPS trips will prevent exceeding the Departure from Nucleate Boiling Ratio (DNBR) safety limit?

A. High flux B. Flux/Pump C. Flux/Flow/Imbalance D. High RCS Temperature Page 38 of 100

Oconee Nuclear Station Question: 39 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor Power = 100%

1KVIB panelboard is de-energized

1) The __(1)__ Voters will NOT actuate their associated safeguards equipment

2) Engineered Safeguards System Instrument Channels are in a __(2)__ out of two trip condition.

A. 1. ODD

2. one B. 1. ODD

2. two C. 1. EVEN

2. one D. 1. EVEN

2. two Page 39 of 100

Oconee Nuclear Station Question: 40 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

1A Main Steam Line Break inside containment occurs Reactor Building Pressure peaks at 22.4 psig

1) The __(1)__ LPSW pumps have received an ES signal to start.

2) Regarding the 1A RBCU, __(2)__ has/have received an ES signal to OPEN.

Which ONE of the following completes the statements above?

A. 1. A and B ONLY

2. 1LPSW-18 ONLY B. 1. A and B ONLY

2. 1LPSW-18 AND 1LPSW-16 C. 1. A, B, AND C

2. 1LPSW-18 ONLY D. 1. A, B, AND C

2. 1LPSW-18 AND 1LPSW-16 Page 40 of 100

Oconee Nuclear Station Question: 41 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor in MODE 1

1) The LOWER Reactor Building Pressure that will result in an automatic start of the Reactor Building Spray pumps is __(1)__ psig.

2) The BWST to LPI and RBS pump suction valves (1LP-21 and 1LP-22) __(2)__.

Which ONE of the following completes the statements above?

A. 1. 4.2

2. are normally OPEN B. 1. 4.2

2. automatically OPEN on ECCS actuation C. 1. 11.5

2. are normally OPEN D. 1. 11.5

2. automatically OPEN on ECCS actuation Page 41 of 100

Oconee Nuclear Station Question: 42 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

1TC locked out 1BS-2 breaker is open and will not close Current conditions:

ES 1 - 8 actuates due to a Large Break LOCA When the Reactor Building Spray system is placed in the recirculation mode:

1) Its purpose is to __ (1) __.

2) The RBS system __ (2) __ be able to perform its safety function.

Which ONE of the following completes the statements above?

A. 1. entrain Iodine thus reducing offsite dose

2. will B. 1. entrain Iodine thus reducing offsite dose

2. will NOT C. 1. minimize hydrogen production due to Zirc water reaction

2. will D. 1. minimize hydrogen production due to Zirc water reaction

2. will NOT Page 42 of 100

Oconee Nuclear Station Question: 43 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

Initial conditions:

Reactor power = 100%

3MS-112 & 3MS-173 (SSRH 3A/3B Controls) are OPEN in MANUAL 3MS-77, 78, 80, 81 (MS to SSRH's) control switches in OPEN Current conditions:

Main Turbine trips

1) 3MS-112 & 3MS-173 will __ (1) __.

2) 3MS-77, 78, 80, 81 will __ (2) __.

Which ONE of the following completes the statements above?

A. 1. close

2. close B. 1. close

2. remain open C. 1. remain open

2. close D. 1. remain open

2. remain open Page 43 of 100

Oconee Nuclear Station Question: 44 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions Initial conditions:

Reactor power = 70% stable Current conditions:

1HPE-6 (Heater 1A1 Bleed Inlet) closed Which ONE of the following predicts the:

1) impact of the malfunction on Feedwater flow assuming no operator action?

2) procedure which will be used to reopen 1HPE-6?

A. 1. higher

2. OP/1/A/1106/23 (High and Low Pressure Extraction)

B. 1. higher

2. OP/1/A/1106/002 (Condensate and FDW system)

C. 1. lower

2. OP/1/A/1106/23 (High and Low Pressure Extraction)

D. 1. lower

2. OP/1/A/1106/002 (Condensate and FDW system)

Page 44 of 100

Oconee Nuclear Station Question: 45 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

Condenser vacuum = 18.5 inches Hg stable 1TA and 1TB de-energized SG levels will be automatically controlled at _______.

Which ONE of the following completes the statement above?

A. 25 inches Startup Range B. 30 inches XSUR C. 50% Operating Range D. 240 inches XSUR Page 45 of 100

Oconee Nuclear Station Question: 46 ILT46 ONS SRO NRC Examination (1 point)

Which ONE of the following utilizes the 1TE ES Power String as its source of electrical power?

A. C LPSW pump B. 1C RBCU C. 1B MDEFWP D. 1B RBS pump Page 46 of 100

Oconee Nuclear Station Question: 47 ILT46 ONS SRO NRC Examination (1 point)

Given the following plant conditions:

The Standby Buses are being powered from the 100 kV line The SL Breakers Auto/Manual Selector switches are in AUTO The TRIP INTERLOCK DEFEAT SWITCH is in the LEE position Which ONE of the following conditions will cause the SL Breakers to open?

A. An undervoltage condition occurs on Standby Bus 1 ONLY.

B. An undervoltage condition would have to occur on BOTH Standby Bus 1 AND Standby Bus 2.

C. The 1st level 100KV Degraded Voltage Relay has been satisfied for 9 seconds AND the 2nd level 100KV Degraded Voltage Relay is now satisfied.

D. The 1st level 100KV Degraded Voltage Relay is satisfied now AND the 2nd level 100KV Degraded Voltage Relay has been satisfied for 9 seconds.

Page 47 of 100

Oconee Nuclear Station Question: 48 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

1PA Battery is inoperable In accordance with SLC 16.8.3 (Power Battery Parameters):

1) The MAXIMUM Completion time allowed to declare the Unit 1 TDEFDW pump inoperable is __ (1) __.

2) Cross connecting __ (2) __ buses is required.

Which ONE of the following completes the statements above?

A. 1. immediately

2. 1PA and 1PB B. 1. immediately

2. 1PA, 2PA and 3PA C. 1. within one hour

2. 1PA and 1PB D. 1. within one hour

2. 1PA, 2PA and 3PA Page 48 of 100

Oconee Nuclear Station Question: 49 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 1200 Reactor power = 100%

ACB-4 Closed LOCA LOOP occurs Time = 1205 Keowee Hydro Unit (KHU)-2 Emergency Lockout occurs Which ONE of the following describes how ECCS systems are being powered at Time

= 1210?

A. KHU-1 through the Overhead power path B. KHU-1 through the underground power path C. CT-5 powered from Lee combustion turbine D. CT-5 powered from Central Switchyard Page 49 of 100

Oconee Nuclear Station Question: 50 ILT46 ONS SRO NRC Examination (1 point)

Which ONE of the following describes the operation of the Unit Vent Radiation Monitors RIA-45 and RIA-46 when the switchover acceptance range setpoint is reached?

RIA-45 will read ___(1)____ and RIA-46 will provide ___(2)____.

A. 1. offscale high

2. only alarm and unit vent radiation level indication B. 1. offscale high

2. the same interlock functions that RIA-45 performs C. 1. ZERO

2. only alarm and unit vent radiation level indication D. 1. ZERO

2. the same interlock functions that RIA-45 performs Page 50 of 100

Oconee Nuclear Station Question: 51 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

A and B LPSW pumps are turned OFF and cannot be restarted 1AP/24 (Loss of LPSW) initiated

1) The LOWEST CRD temperature that will require a Reactor trip is __(1)__ °F in accordance with 1AP/20 (Loss of Component Cooling).

2) RCW system temperatures would be expected to __(2)__.

Which ONE of the following completest the statements above?

A. 1. 140

2. increase B. 1. 140

2. remain unchanged C. 1. 180

2. increase D. 1. 180

2. remain unchanged Page 51 of 100

Oconee Nuclear Station Question: 52 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor Power = 100%

Instrument Air pressure = 63 psig slowly decreasing Immediate Manual Actions of the EOP will be performed after AP/22 (Loss of Instrument Air) directs tripping the _______.

Which ONE of the following completes the statement above?

A. Reactor ONLY B. Reactor and Main Turbine ONLY C. Reactor and Main Feedwater Pumps ONLY D. Reactor, Main Turbine, AND the Main Feedwater Pumps Page 52 of 100

Oconee Nuclear Station Question: 53 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor trip from 100% due to loss of all Main Feedwater 1FDW-316 pneumatic supply line has ruptured and the valve cannot be operated from Control Room Enclosure 5.27 (Alternate Methods of Feeding the Steam Generator) in progress SRO notified that the startup path to the 1B SG CANNOT be used Which ONE of the following describes how RCS temperature will be controlled?

A. Using ONLY the 1A SG B. Use 1A SG AND manually throttle 1FDW-316 C. Use 1A SG AND feed 1B SG with Alternate Units EFDW D. Align TDEFWP to 1B SG and use 1MS-94 spindle to throttle TDEFWP speed to control flow to 1B SG Page 53 of 100

Oconee Nuclear Station Question: 54 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 1200 Reactor in MODE 5 RCS Loops dropped Pressurizer level = 340 stable RB Cavity washdown in progress RB Purge in progress Reactor Building Sump is being pumped Time = 1205 Pressurizer level 322 inches decreasing 1RIA-49 (Reactor Building High Gas) in HIGH alarm

1) The Containment Evacuation alarm __(1)__ AUTOMATICALLY actuate as a result of the 1RIA-49 HIGH alarm.

2) __(2)__ is the procedure that will be entered FIRST.

Which ONE of the following completes the statements above?

A. 1. will

2. AP/26 (Loss of Decay Heat Removal)

B. 1. will

2. AP/2 (Excessive RCS Leakage)

C. 1. will NOT

2. AP/26 (Loss of Decay Heat Removal)

D. 1. will NOT

2. AP/2 (Excessive RCS Leakage)

Page 54 of 100

Oconee Nuclear Station Question: 55 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor in MODE 5 RB Main Purge in operation Which ONE of the following will cause the RB Main Purge Fan to trip OFF?

A. Suction pressure = 5 inches of water vacuum B. 1RIA-45, UNIT VENT GAS NORM, reaches its ALERT setpoint C. Statalarm 1SA9/B-3, RBV PURGE INLET TEMPERATURE LOW, alarms D. 1PR-3 (RB PURGE CONTROL) green CLOSED light is lit and red OPEN light is off on 1VB2 Page 55 of 100

Oconee Nuclear Station Question: 56 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Startup in progress Estimated Critical Rod Position (ECP) calculation as follows:

o ECP = Gp 7 @ 12% withdrawn (wd) o -0.75% delta K/K = Gp 6 @ 64% wd o -1% delta K/K = Gp 6 @ 55% wd Safety Rod withdrawal is about to begin In accordance with AD-OP-ALL-0203 (Reactivity Management), which ONE of the following describes the EARLIEST condition where criticality should be expected?

Withdrawing Control Rods and ________.

A. Group 1 > 0% wd B. Group 6 > 55% wd C. Group 6 > 64% wd D. Group 7 > 12% wd Page 56 of 100

Oconee Nuclear Station Question: 57 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor has tripped from 100%

ALL Condensate, Feedwater, AND Emergency Feedwater pumps are unavailable BOTH 1A and 1B SGs are dry RCS temperature = 584°F slowly increasing RCS pressure = 2044 psig slowly increasing

1) Assuming NO operator actions, RCS __(1)__ will stop increasing FIRST.

2) The EOP will direct using __(2)__ to remove core decay heat.

Which ONE of the following completes the statements above?

A. 1. pressure

2. HPI Forced Cooling B. 1. pressure

2. SSF ASW C. 1. temperature

1. HPI Forced Cooling D. 1. temperature

2. SSF ASW Page 57 of 100

Oconee Nuclear Station Question: 58 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial Conditions:

Reactor Power = 100%

1B RPS channel in Manual Bypass due to failed RB pressure transmitter Current Conditions:

1NI-7 fails HIGH The 1C RPS channel:

1) __(1)__ AUTOMATICALLY trip.

2) __(2)__ be placed in Manual Bypass in accordance with OP/1/A/1105/014 (Control Room Instrumentation).

Which ONE of the following completes the statements above?

A. 1. did

2. will B. 1. did

2. will NOT C. 1. did NOT

2. will D. 1. did NOT

2. will NOT Page 58 of 100

Oconee Nuclear Station Question: 59 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 90% stable 1A and 1B Main FDW Control valves are in HAND Controlling Feedwater valve P fails LOW

1) Steam Generator levels __(1)__ increase.

2) IF the conditions above result in a Reactor trip, the FDW Control Valve ICS Hand/Auto stations will __(2)__ .

Which ONE of the following completes the statements above?

ASSUME NO OPERATOR ACTIONS A. 1. will

2. remain in HAND B. 1. will

2. revert to AUTO C. 1. will NOT

2. remain in HAND D. 1. will NOT

2. revert to AUTO Page 59 of 100

Oconee Nuclear Station Question: 60 ILT46 ONS SRO NRC Examination (1 point)

Unit 2 initial conditions:

Reactor in MODE 6 Fuel Transfer Canal slightly above 21.34 mark on canal wall RB Hatch closed RB Purge is operating 2SF-1 AND 2SF-2 are open Current conditions:

RB Purge trips Which ONE of the following predicts the response of actual Fuel Transfer Canal level?

Fuel Transfer Canal level will A. decrease then remain constant B. initially decrease then return to previous level C. increase then remain constant D. initially increase then return to previous level Page 60 of 100

Oconee Nuclear Station Question: 61 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

Turbine Bypass Valves (TBVs) in HAND Current Conditions 1KU is de-energized

1) The TBVs are __(1)__.

2) The TBVs __(2)__ manually operable from the Control Room.

Which ONE of the following completes the statements above ?

A. 1. closed

2. are B. 1. 50% open

2. are C. 1. closed

2. are NOT D. 1. 50% open

2. are NOT Page 61 of 100

Oconee Nuclear Station Question: 62 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

0359:45 Reactor power = 70% stable 1B CBP trips 0400:00 Main FDW Pump suction pressure = 235 psig decreasing 0401:00 Main FDW Pump suction pressure = 230 psig decreasing 0401:30 Main FDW Pump suction pressure = 225 psig stable Based on the above conditions, complete the following statements:

1) Of the times listed above, 1C-61 (Cond Cooler Bypass Control) will first open at

__ (1) __.

2) At 0401:35, the entry conditions for the EOP __ (2) __ met.

Which ONE of the following completes the statements above?

A. 1. 0400:00

2. are B. 1. 0400:00

2. are NOT C. 1. 0401:30

2. are D. 1. 0401:30

2. are NOT Page 62 of 100

Oconee Nuclear Station Question: 63 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

1A GWD tank release in progress 1RIA-37 HIGH alarm actuates 1SA-8/B9 (Process Monitor Radiation High) actuates Which ONE of the following describes the:

1) impact on the Gaseous Waste Disposal (GWD) system?

2) procedure that contains actions that must be performed prior to re-initiating the release?

A. 1. Closes 1A GWD tank inlet AND outlet valves

2. OP/1-2/A/1104/018 (GWD System) ONLY B. 1. Closes 1A GWD tank inlet AND outlet valves

2. AP/18 (Abnormal Release of Radioactivity) and OP/1-2/A/1104/018 (GWD System) ONLY C. 1. Closes 1A GWD tank outlet valves ONLY

2. OP/1-2/A/1104/018 (GWD System) ONLY D. 1. Closes 1A GWD tank outlet valves ONLY

2. AP/18 (Abnormal Release of Radioactivity) and OP/1-2/A/1104/018 (GWD System) ONLY Page 63 of 100

Oconee Nuclear Station Question: 64 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

PT/0/A/0230/001, Radiation Monitor Check completed on Unit 1 1RIA-57 = .75 R/HR Which ONE of the following is an indication of a satisfactory source check?

A. Alert Alarm Actuation ONLY B. Alert AND High Alarm Actuation C. Area Monitor Fault Alarm Actuation D. Indication remains at .75 R/HR with no alarms Page 64 of 100

Oconee Nuclear Station Question: 65 ILT46 ONS SRO NRC Examination (1 point)

IA Pressure vs. Time Based on the graph above, which ONE of the following describes the EARLIEST time at which SA-141 (SA to IA Controller) will automatically open?

A. 1207 B. 1210 C. 1212 D. 1215 Page 65 of 100

Oconee Nuclear Station Question: 66 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

The BOP determines that the Steam Packing Exhauster is OFF

1) The BOP will communicate this to the crew using a crew __ (1) __.

2) The above communication __ (2) __ required to be 3-way.

Per SOMP 1-07 (Control Room Oversight) AND OMP 1-24 (Operations Communications Standards), which ONE of the following completes the statements above?

A. 1. update

2. is B. 1. update

2. is NOT C. 1. brief

2. is D. 1. brief

2. is NOT Page 66 of 100

Oconee Nuclear Station Question: 67 ILT46 ONS SRO NRC Examination (1 point)

RUNBACKS LOAD LIMITS REACTOR COOLANT ASYM FDW UNIT IN BY BY B\Y ON PUMP FLOW RODS PUMP TRACK FDW TURBINE REACTOR HIGH STATOR REACTOR GEN BKR PWR/LOAD FDW TURBINE REACTOR COOLANT TRIP TRIP UNBAL MANUAL MANUAL MANUAL C/FDW RATE SET PRESSURE 0 0  % / MIN

% / HR RATE RATE HOLD

% / Min  % / HR TURBINE TURBINE MAXIMUM FAST INCREASE DECREASE LOAD UNLOAD RUNBACK SLOW Note: Drawing not representative of actual plant conditions.

Given the following Unit 1 conditions:

Initial conditions:

Time = 0400 Reactor power = 100% decreasing Control Rod Group 1 Rod 3 = 0% withdrawn Current conditions:

Time = 0430 Reactor power = 68% decreasing 1B1 RCP trips

1) At 0400, the power to which the ICS is running the plant back is displayed in the

__ (1) __ window. (refer to the drawing above)

2) After the RCP trips, the unit __ (2) __ automatically stabilize at the required reactor power for plant conditions.

Which ONE of the following completes the statements above?

A. 1. upper

2. will B. 1. upper

2. will NOT C. 1. lower

2. will D. 1. lower

2. will NOT Page 67 of 100

Oconee Nuclear Station Question: 68 ILT46 ONS SRO NRC Examination (1 point)

Given the following plant conditions:

Unit 1 Reactor power = 100%

Unit 2 Reactor in MODE 3 In accordance with OMP 2-1 Attachment D (SSF Staffing Requirements), which ONE of the following:

1) states restrictions on the RO designated to man the SSF when NO SSF event is in progress?

2) describes the minimum actions required for one of the designated SSF RO's to take a short trip to the station canteen?

A. 1. MUST remain in the Horseshoe area of the Control Room

2. The RO must be relieved by another licensed operator that is NOT part of the minimum staffing before leaving the designated area B. 1. MUST remain in the Horseshoe area of the Control Room

2. A method of communication must be established to enable notification of the requirement to activate the SSF before leaving the designated area C. 1. Can be anywhere inside the Control Room CAD doors

2. The RO must be relieved by other licensed operator that is NOT part of the minimum staffing before leaving the designated area D. 1. Can be anywhere inside the Control Room CAD doors

2. A method of communication must be established to enable notification of the requirement to activate the SSF before leaving the designated area Page 68 of 100

Oconee Nuclear Station Question: 69 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Startup in progress The OATC Reactor Operator manipulating Control Rods is training an individual on OJT from License Class 1SA-03/E-7 (TO Bearing Header Pressure Low) actuates In accordance with AD-OP-ALL-0203 (Reactivity Management):

1) stopping control rod withdrawal __ (1) __ required.

2) the OATC __ (2) __ allowed to peer-check the withdrawal of control rods being done by the trainee.

Which ONE of the following completes the statements above?

A. 1. is

2. is B. 1. is

2. is NOT C. 1. is NOT

2. is D. 1. is NOT

2. is NOT Page 69 of 100

Oconee Nuclear Station Question: 70 ILT46 ONS SRO NRC Examination (1 point)

In accordance with OMP 1-02 (Rules of Practice), which ONE of the following describes:

1) a condition which would allow Independent Verification of a single valve to be waived?

2) the minimum level of approval required?

A. 1. Dose received will be = 14 mr for a single check

2. Control Room Supervisor B. 1. Valve located in a room where the area dose rate = 878 mr/hr

2. Control Room Supervisor C. 1. Dose received will be = 14 mr for a single check

2. Shift Manager D. 1. Valve located in a room where the area dose rate = 878 mr/hr

2. Shift Manager Page 70 of 100

Oconee Nuclear Station Question: 71 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

RCS Pressure = 2150 psig stable Pressurizer Temperature = 628°F stable Which ONE of the following describes the:

1) INITIAL plant response to energizing ALL Pressurizer heaters?

2) RCS pressure setpoint (psig) that will result in 1RC-1 opening?

A. 1. RCS Pressure will increase

2. 2155 B. 1. Pressurizer temperature will increase

2. 2155 C. 1. RCS Pressure will increase

2. 2205 D. 1. Pressurizer temperature will increase

2. 2205 Page 71 of 100

Oconee Nuclear Station Question: 72 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor in MODE 6 RB Purge in progress Current conditions:

IRIA-47 (RB Particulate) in HIGH alarm AP/18, Abnormal Release of Radioactivity is initiated

1) RB Purge __(1)__ automatically terminate.

2) AP/18 __(2)__ direct the evacuation of personnel from the RB A. 1. will

2. does B. 1. will

2. does NOT C. 1. will NOT

2. does D. 1. will NOT

2. does NOT Page 72 of 100

Oconee Nuclear Station Question: 73 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

3A GWD gas tank release in progress Release is at 2/3 Station Limit

1) 1RIA-45 High and Alert setpoints will be set at __ (1) __ the normal 1/3 Station Limit as listed in PT/0/A/230/001 (Radiation Monitor Check).

2) If 1RIA-45 High alarm setpoint is reached, the 3A GWD gas tank release __(2)__

AUTOMATICALLY terminate.

Which ONE of the following completes the statements above?

A. 1. double

2. will B. 1. double

2. will NOT C. 1. half

2. will D. 1. half

2. will NOT Page 73 of 100

Oconee Nuclear Station Question: 74 ILT46 ONS SRO NRC Examination (1 point)

Given the following Plant conditions:

Unit 1 = 100%

Unit 2 has an event in progress that requires SSF ASW activation

1) In accordance with OMP 2-1 (Duties and Responsibilities of On-Shift Operations Personnel), the __(1)__ BOP will be dispatched to perform AP/25 (SSF Activation).

2) Prior to leaving the Control Room for the SSF, AP/25 directs tripping __(2)__

RCP(s).

Which ONE of the following completes the statements above?

A. 1. Unit 1

2. ALL B. 1. Unit 1

2. all but ONE C. 1. Unit 2

2. ALL D. 1. Unit 2

2. all but ONE Page 74 of 100

Oconee Nuclear Station Question: 75 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor in MODE 6 LPI aligned in NORMAL Mode RCS level = 75 on LT-5 stable 1B LPI Pump tagged out Current conditions:

RCS level = 72 on LT-5 decreasing

1) In accordance with OP/1/A/1104/004 (LPI System), the __(1)__ LPI pump will be in operation?

2) In accordance with AP/26 (Loss of Decay Heat Removal), which ONE of the following describes the reason ALL LPI pumps are initially secured?

A. 1. 1C

2. prevent pump damage due to loss of suction B. 1. 1A

2. prevent pump damage due to loss of suction C. 1. 1C

2. determine if leak source is on the discharge of the LPI pumps D. 1. 1A

2. determine if leak source is on the discharge of the LPI pumps Page 75 of 100

Oconee Nuclear Station Question: 76 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

RCS cooldown in progress RCS temperature = 310 °F slowly decreasing Current conditions:

Both the 1A and 1B HPI pumps have failed AP/14 (Loss of HPI Normal Makeup and/or RCP Seal Injection) in progress 1C HPI pump has been aligned to provide RCS makeup

1) In accordance with OP/1/A/1104/002 (HPI System), aligning the 1C HPI pump as the RCS Makeup pump __(1)__ make the 1HP-120 Travel Stop inoperable

2) In accordance with the basis of Tech Spec 3.4.12 (LTOP), with ALL LTOP Administrative Controls in place, additional operator actions to mitigate an LTOP event are required within __(2)__ minutes of the event initiation.

Which ONE of the following completes the statements above?

A. 1. does

2. 10 B. 1. does

2. 25 C. 1. does NOT

2. 10 D. 1. does NOT

2. 25 Page 76 of 100

Oconee Nuclear Station Question: 77 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

1A Main FDWP has tripped Reactor Power = 76% decreasing RCS Pressure = 2215 psig increasing 1RC-1 (Pressurizer Spray) indicates Closed

1) 1RC-1 __(1)__ operating as designed.

2) In accordance with the basis of Tech Spec 2.0 (Safety Limits), the RCS pressure Safety Limit __(2)__ take credit for the operation of 1RC-1.

Which ONE of the following completes the statements above?

A. 1. is

2. does B. 1. is

2. does NOT C. 1. is NOT

2. does D. 1. is NOT

2. does NOT Page 77 of 100

Oconee Nuclear Station Question: 78 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 90% decreasing SGTR tab in progress Pressurizer level = 205 inches slowly increasing

1) In accordance with plant procedures, 1HP-26 __(1)__ be used to maintain Pzr level PRIOR to tripping the Reactor.

2) With Pzr level being maintained, the MAXIMUM power level at which the SGTR tab will direct tripping the REACTOR is __(2)__ %.

Which ONE of the following completes the statements above?

A. 1. can

2. 18 B. 1. can

2. 5 C. 1. can NOT

2. 18 D. 1. can NOT

2. 5 Page 78 of 100

Oconee Nuclear Station Question: 79 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor Power = 100%

1KVIC power supply is transferred to 1KRB in support of Maintenance on 1DIC inverter Current conditions:

1DIC inverter work is completed and it is ready to be aligned to 1KVIC

1) In accordance with the basis of Tech Spec 3.8.6 (Inverters-Operating), 1KVIC Panelboard is __(1)__ .

2) In accordance with the basis of Tech Spec 3.8.8 (Distribution Systems-Operating),

the 1DIC Inverter is __(2)__.

A. 1. operable

2. operable B. 1. operable

2. inoperable C. 1. inoperable

2. operable D. 1. inoperable

2. inoperable Page 79 of 100

Oconee Nuclear Station Question: 80 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

BOP and OATC are only ROs available Degrading instrument air pressure results in a manual Reactor Trip in accordance with AP/22 (Loss of Instrument Air)

During the transient, indications of a Main Steam Line Break (MSLB) were observed RCS pressure decreased to 1437 psig and then began to increase

1) In accordance with OMP 1-18 (Implementation Standard During Abnormal and Emergency Events) the Procedure Director will direct that AP/22 be performed in parallel with the EOP __(1)__.

2) In accordance with Rule 5 (Main Steam Line Break) HPI can be throttled once Pressurizer level has returned to __ (2) __.

Which ONE of the following completes the statements above?

A. 1. immediately after Immediate Manual Actions and Symptoms Check are completed

2. on scale and increasing B. 1. immediately after Immediate Manual Actions and Symptoms Check are completed

2. > 100 inches C. 1. ONLY after Rule 5 (Main Steam Line Break) and EOP Enclosure 5.1 (ES Actuation) have been completed

2. on scale and increasing D. 1. ONLY after Rule 5 (Main Steam Line Break) and EOP Enclosure 5.1 (ES Actuation) have been completed

2. > 100 inches Page 80 of 100

Oconee Nuclear Station Question: 81 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor Power = 45% stable AP/34 (Generator Grid Disturbance) in progress Generator Output = 350 MWe Hydrogen pressure = 60 psig In accordance with AP/34,

1) The MAXIMUM limit on MVARs is approximately __(1)__.

2) If operation in the acceptable region of the Generator Capability Curve cannot be maintained, __(2)__.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. 725

2. trip the Reactor B. 1. 725

2. Open PCB-20 and PCB-21 C. 1. 475

2. trip the Reactor D. 1. 475

2. Open PCB-20 and PCB-21 Page 81 of 100

Oconee Nuclear Station Question: 82 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 85% stable Delta Tc in HAND Current conditions:

ICS runback in progress Reactor power as indicated below POWER RANGE NIS NI 5 NI 6 NI 7 NI 8

% FP  % FP  % FP  % FP 84.8 83.1 75.6 86.4

+60 +60 +60 125 +60 125 125 125 100 +40 100 +40 100 +40 100 +40 80 +20 80 +20 80 +20 80 +20 60 0 60 0 60 0 60 0 40 -20 40 -20 40 -20 40 -20 20 -40 20 -40 20 -40 20 -40 0 -60 0 -60 0 -60 0 -60 0.00 0.00 0.00 0.00

% IMB  % IMB  % IMB  % IMB 0

Which ONE of the following describes:

1) the reason for the ICS runback?

2) the consequences of operating the unit under the conditions described above?

A. 1. Dropped Control Rod

2. Allowable Thermal Power limits of Tech Spec 3.4.4 (RCS Loops MODES 1 and 2) could be exceeded B. 1. Dropped Control Rod

2. Maximum Linear Heat Rate could be exceeded C. 1. RCP trip

2. Allowable Thermal Power limits of Tech Spec 3.4.4 (RCS Loops MODES 1 and 2) could be exceeded D. 1. RCP trip

2. Minimum Departure from Nucleate Boiling Ration limits could be exceeded Page 82 of 100

Oconee Nuclear Station Question: 83 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 0400 Reactor has been tripped due to SGTR in the 1A SG Time = 0430 Feedwater to the 1A SG is isolated 1A SG level = 273 inches XSUR increasing Time = 0500 1A SG level = 293 inches XSUR increasing Time = 0530 1A SG reaches the Water in Steam Line Level In accordance with the SGTR tab:

1) At 0500, EOP Enclosure 5.22 (SG Blowdown) __(1)__ be used to reduce 1A SG level.

2) At 0530, __(2)__ steaming the 1A SG.

Which ONE of the following completes the statements above?

A. 1. will NOT

2. continue B. 1. will NOT

2. stop C. 1. will

2. continue D. 1. will

2. stop Page 83 of 100

Oconee Nuclear Station Question: 84 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Time = 0400 Reactor power = 80% stable Control Rods Group 7 = 83% withdrawn Group 7 Rod 3 will not move and is declared inoperable Current conditions:

Time = 0500 Reactor power = 80% STABLE 1SA7 E/9 CR ROD WITHDRAWAL LIMIT comes into alarm Group 7 Control Rods are at 40% withdrawn In accordance with Tech Spec 3.2.1 (Regulating Rod Position Limits)

1) Boration __(1)__ have to be initiated within 15 minutes.

2) If Control Rods are not restored to the acceptable region of the rod curves provided in the COLR, the reactor must be in MODE 3 no later than __(2)__.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. does

2. 1900 B. 1. does

2. 1700 C. 1. does NOT

2. 1900 D. 1. does NOT

2. 1700 Page 84 of 100

Oconee Nuclear Station Question: 85 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

Breaker Status o ACB 4 - Closed o PCB 8 - Open o PCB 9 - Open SA-2, C-1 KEOWEE PCB 9 is in alarm SA-2, B-1 DACUS BL. KEOWEE TIE PCB 8 is in alarm

1) Keowee Hydro Unit-2 __(1)__ be started in AUTOMATIC from the Control Room.

2) In accordance with the basis of Tech Spec 3.8.1 (AC Systems-Operating), Keowee Hydro Unit -1 is currently __(2)__.

Which ONE of the following completes the statements above?

A. 1. can

2. OPERABLE B. 1. can

2. INOPERABLE C. 1. can NOT

2. OPERABLE D. 1. can NOT

2. INOPERABLE Page 85 of 100

Oconee Nuclear Station Question: 86 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit conditions:

RCS temperature = 240°F slowly decreasing RCS pressure = 275 psig slowly decreasing In accordance with Tech Spec 3.4.12 (LTOP System)

1) Pressurizer level __(1)__ required to be <220 inches?

2) When Pressurizer level does NOT meet the requirements of Tech Spec 3.4.12,

__(2)__ is required?

REFERENCE PROVIDED A. 1. is

2. shutting down to MODE 5 in accordance with LCO 3.0.3 B. 1. is

2. establishing a dedicated LTOP operator within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. 1. is NOT

2. shutting down to MODE 5 in accordance with LCO 3.0.3 D. 1. is NOT

2. establishing a dedicated LTOP operator within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Page 86 of 100

Oconee Nuclear Station Question: 87 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 0600 Reactor power = 90%

RPS Channel B High RB pressure fails HIGH RPS Channel B is Placed in Manual Bypass Time = 0800 RPS Channel C High RB pressure fails LOW Time = 0815 RPS Channel C placed in TRIP Time = 0830 RPS Channel A High RB pressure fails LOW

1) An automatic Reactor trip __(1)__ occurred.

2) TS 3.3.1 (RPS Instrumentation) requires that all CRD trip breakers be open no later than __(2)__.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. has

2. 1430 B. 1. has

2. 2030 C. 1. has NOT

2. 1430 D. 1. has NOT

2. 2030 Page 87 of 100

Oconee Nuclear Station Question: 88 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor Power = 100%

While performing SR 3.3.5.2, Manual ES Setpoint Verification, SPOC determines that Reactor Building Pressure High as found setpoints to be as follows:

A = 3.53 psig B = 4.04 psig C = 4.09 psig

1) The Actual Setpoint for ES RB Pressure High is __(1)__ psig.

2) ALL Tech Spec 3.3.5 (ESPS Input Instrumentation) Conditions that must be entered are Condition(s) __(2)__.

Which ONE of the following completes the statement above?

REFERENCE PROVIDED A. 1. 3.0

2. A and B B. 1. 3.0

2. A ONLY C. 1. 3.5

2. A and B D. 1. 3.5

2. A ONLY Page 88 of 100

Oconee Nuclear Station Question: 89 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Startup in progress Reactor in MODE 3 1A RBS pump inoperable

1) Tech Spec 3.6.5 (Reactor Building Spray and Cooling Systems) LCO __(1)__ met.

2) When Tech Spec 3.6.5 LCO is NOT met, Unit 1 entry into MODE 2 __(2)__

allowed.

Which ONE of the following completes the above statement?

A. 1. is

2. is B. 1. is

2. is NOT C. 1. is NOT

2. is D. 1. is NOT

2. is NOT Page 89 of 100

Oconee Nuclear Station Question: 90 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 0700 Reactor power = 75% stable 1A RBCU INOPERABLE Time = 0800 1SA/9 A-6 REACTOR BUILDING NORMAL SUMP LEVEL HIGH/LOW in alarm 1C RBCU flow indications o Flow = 270 gpm o Inlet Flow = 560 gpm Time = 0810 1LPSW-22 (1C RBCU INLET) and 1LPSW-24 (RBCU 1C OUTLET) are closed RB Sump level has stopped increasing

1) At 0800, 1SA/9 D-9 RBCU C COOLER RUPTURE __(1)__ be in alarm.

2) At 0810, Containment is __(2)__ in accordance with Tech Spec 3.6.1 (Containment).

Which ONE of the following completes the statements above?

A. 1. should

2. OPERABLE B. 1. should

2. INOPERABLE C. 1. should NOT

2. OPERABLE D. 1. should NOT

2. INOPERABLE Page 90 of 100

Oconee Nuclear Station Question: 91 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 1200:

Reactor startup in progress Reactor power = 6E-3% stable on all WR NIs 1NI-1 and 1NI-3 Source Range Channels are unavailable Time = 1205:

1NI-2 Source Range power supply fails

1) 1NI-1 and 1NI-3 are located in RPS channels A and __(1)__ respectively.

2) At Time = 1205, Tech Specs __(2)__ allow the power increase to continue to greater than 5% power.

Which ONE of the following completes the statements above?

A. 1. B

2. does B. 1. B

2. does NOT C. 1. C

2. does D. 1. C

2. does NOT Page 91 of 100

Oconee Nuclear Station Question: 92 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

Reactor in MODE 6 Core offload in progress Main Fuel Bridge is withdrawing a fuel assembly

1) A loss of the __(1)__ interlock would increase the risk of fuel assembly damage during withdrawal.

2) In accordance with MP/0/A/1500/009 (Reactor Bridge Operation), __(2)__ must authorize bypassing the above interlock.

Which ONE of the following completes the statement above?

A. 1. Fuel Overload (TS-1)

2. BOTH the Fuel Handling Supervisor AND the Refueling SRO B. 1. Fuel Overload (TS-1)

2. EITHER the Fuel Handling Supervisor OR the Refueling SRO C. 1. Fuel Hoist Up/Down (TS-2)

2. BOTH the Fuel Handling Supervisor AND the Refueling SRO D. 1. Fuel Hoist Up/Down (TS-2)

2. EITHER the Fuel Handling Supervisor OR the Refueling SRO Page 92 of 100

Oconee Nuclear Station Question: 93 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Loss of all feedwater has occurred The Loss Of Heat Transfer (LOHT) tab is in progress The RO is lining up to feed the SGs with the Condensate Booster Pumps (CBP)

The RO has just selected OFF for both channels on AFIS headers A and B.

1) The next procedural step in Rule 3 is to open the __(1)__ block and control valves to allow CBP flow when Steam Generator pressure is decreased.

2) Once Condensate Booster Pump feed has been established in accordance with Rule 3, the procedure director will __(2)__ the LOHT tab.

Which ONE of the following completes the statements above?

A. 1. Main

2. wait until EFDW has been made available before continuing in B. 1. Main

2. continue in C. 1. Startup

2. wait until EFDW has been made available before continuing in D. 1. Startup

2. continue in Page 93 of 100

Oconee Nuclear Station Question: 94 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Maintenance is being performed on Unit 1 condensate system The clearance for the section of piping connected to the component is such that the piping can be vented but not drained.

In accordance with SOMP 2-1 (Safety Tagging And Configuration Control)

1) An SRO with an Inactive license __(1)__ allowed to sign the WOTA Ready for Work.

2) Zero Energy Comments __(2)__ have to be entered into ST-2 prior to setting the WOTA Ready for Work.

Which ONE of the following completes the statements above?

A. 1. is

2. do B. 1. is

2. do NOT C. 1. is NOT

2. do D. 1. is NOT

2. do NOT Page 94 of 100

Oconee Nuclear Station Question: 95 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

SGTR tab in progress RCS temperature = 530°F stable 1A SG isolated 3 RCPs operating HPI pump suction aligned to BWST Group 3 Rod 2 100% withdrawn

1) __ (1) __ tab of the EOP will be utilized to cooldown to LPI.

2) In accordance with the EOP tab above, the lowest RCS temperature allowed prior to performing a Shutdown Margin verification is __(2)__ °F.

Which ONE of the following completes the statements above?

A. 1. SGTR

2. 240 B. 1. SGTR

2. 450 C. 1. FCD

2. 240 D. 1. FCD

2. 450 Page 95 of 100

Oconee Nuclear Station Question: 96 ILT46 ONS SRO NRC Examination (1 point)

1) When Tech Spec 3.2.1 (Regulating Rods Position Limits) requires RCS Boration, the basis of the spec allows the SRO to direct boration using __(1)__.

2) The consequences of being in the Unacceptable region of the rod curve is that

__(2)__.

Which ONE of the following completes the statements above?

A. 1. 1A BHUT

2. required shutdown margin may not exist B. 1. 1A BHUT

2. Quadrant Power Tilt limits may be exceeded C. 1. BWST

2. required shutdown margin may not exist D. 1. BWST

2. Quadrant Power Tilt limits may be exceeded Page 96 of 100

Oconee Nuclear Station Question: 97 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor in Mode 6 Defueling in progress 1RIA-3 (Fuel Transfer Canal Monitor) = 4 mr/hr stable Main Fuel Bridge Area Monitor = 6 mr/hr stable Current conditions:

1RIA-3 local reading = 0 mr/hr 1RIA-3 View Node indication is magenta The Refueling SRO will determine that Fuel Handling activities in the Reactor Building may ______ in accordance with OP/1/A/1502/007 (Operations Defueling/Refueling Responsibilities)?

Which ONE of the following completes the statement above?

A. NOT continue until a portable area monitor with local alarm capability is in place.

B. continue because only the Main Fuel Bridge Area Monitor is required.

C. NOT continue until continuous RP coverage is present on the Main Fuel Bridge.

D. continue provided 1RIA-49 (RB Normal Gas) is operable.

Page 97 of 100

Oconee Nuclear Station Question: 98 ILT46 ONS SRO NRC Examination (1 point)

Given the following plant conditions:

Shift is preparing for ONE (1) GWR release of the 1A GWD tank at the 1/3 Station Limit The release will be through the P/A/C filter 1A GWD tank holdup time is 41 days Which ONE of the following describes the:

1) MINIMUM level of authority for approval in accordance with OP/1-2/A/1104/018 (GWD System)?

2) SLC bases for limiting the Curie content of the Gaseous Waste Disposal (GWD)

Tanks?

A. 1. OSM

2. limits Whole Body exposure of individual at the nearest exclusion boundary to < 0.5 Rem in the event of a GWD tank rupture.

B. 1. OSM

2. limits Whole Body exposure of individual at the nearest exclusion boundary to < 100 mrem during a planned GWD tank release.

C. 1. SRO

2. limits Whole Body exposure of individual at the nearest exclusion boundary to < 0.5 Rem in the event of a GWD tank rupture.

D. 1. SRO

2. limits Whole Body exposure of individual at the nearest exclusion boundary to < 100 mrem during a planned GWD tank release.

Page 98 of 100

Oconee Nuclear Station Question: 99 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

SGTR on the 1A SG SGTR tab is in progress TBVs are not available RCS Temperature = 530oF stable Current conditions:

1A SG is approaching overfill

1) When directing the local operation of the ADV on the 1A SG to prevent overfill, the TS limit for cooldown rate __(1)__ be exceeded.

2) If while steaming the affected SG, SCM decreases to 0 oF, the SGTR tab directs the crew to GO TO __(2)__ tab.

Which ONE of the following completes the statements above?

A. 1. can

2. Loss Of Subcooling Margin (LOSCM)

B. 1. can

2. LOCA Cooldown C. 1. can NOT

2. LOSCM D. 1. can NOT

2. LOCA Cooldown Page 99 of 100

Oconee Nuclear Station Question: 100 ILT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time = 1200 Unit shutting down due to a 30 gpm tube leak in "1A" SG Time = 1203 Unit trips due to a loss of Main Feedwater Emergency Feedwater is NOT available Time = 1207 NEO reports one Main Steam Relief Valve on the 1B SG stuck open Unit 2 TDEFWP aligned and feeding Unit 1 Steam Generators 1A SG tube leak = 200 gpm stable

1) The conditions present at 1200 __ (1) ___ require an emergency classification within 15 minutes.

2) At time = 1207 the emergency classification is __ (2) ___.

Assume no additional failures occur AND that Emergency Coordinator Judgment is NOT used as a reason for classification.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. would

2. ALERT B. 1. would

2. SITE AREA EMERGENCY C. 1. would NOT

2. ALERT D. 1. would NOT

2. SITE AREA EMERGENCY Page 100 of 100

Examination KEY for: ILT46 ONS SRO NRC Examin Question Answer Number 1 B 2 B 3 C 4 B 5 C 6 C 7 B 8 B 9 D 10 A 11 D 12 A 13 A 14 A 15 C 16 D 17 C 18 A 19 C 20 B 21 B 22 D 23 A 24 A 25 A Printed 10/3/2014 10:16:05 AM Page 1 of 4

Examination KEY for: ILT46 ONS SRO NRC Examin Question Answer Number 26 A 27 B 28 B 29 C 30 C 31 D 32 D 33 C 34 D 35 D 36 C 37 A 38 C 39 D 40 C 41 C 42 B 43 B 44 C 45 D 46 C 47 B 48 B 49 A 50 D Printed 10/3/2014 10:16:05 AM Page 2 of 4

Examination KEY for: ILT46 ONS SRO NRC Examin Question Answer Number 51 D 52 C 53 B 54 B 55 D 56 A 57 A 58 D 59 B 60 A 61 A 62 A 63 C 64 D 65 D 66 B 67 D 68 D 69 B 70 A 71 D 72 C 73 D 74 C 75 D Printed 10/3/2014 10:16:05 AM Page 3 of 4

Examination KEY for: ILT46 ONS SRO NRC Examin Question Answer Number 76 A 77 D 78 B 79 B 80 C 81 B 82 B 83 D 84 A 85 C 86 B 87 D 88 A 89 B 90 A 91 A 92 A 93 C 94 A 95 B 96 C 97 A 98 C 99 A 100 A Printed 10/3/2014 10:16:05 AM Page 4 of 4