Text

301 Exam Report Items - SRO as Given Written Exam
	ML21174A045
Person / Time
Site:	Oconee
Issue date:	06/23/2021
From:	; NRC/RGN-II
To:	;
References
	Download: ML21174A045 (111)
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Question:

(1 point) 1 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:

Unit 2 tripped spuriously 25 minutes ago

All systems responded as expected

The CRS has entered OP/2/A/1102/010 (Controlling Procedure for Unit Shutdown), Enclosure 4.14 (S/D to Mode 3 Following Rx Trip or Rapid S/D).14 requires that RCS temperature is maintained > a MINIMUM of __(1)__ due to __(2)__concerns.

A.

1. 550 °F

2. Shutdown Margin B.

1. 550 °F

2. SSF availability C.

1. 532 °F

2. SSF availability D.

1. 532 °F

2. Shutdown Margin Page 1 of 100 ML21174A045

Question:

(1 point) 2 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial Conditions:

Reactor power = 100%

Current conditions:

1RC-66 (PORV) indicates partially open 1RC-4 will NOT close from the control room RCS pressure is being maintained 2200 psig and stable via constant makeup flow

1) The Control Room Staff is required to enter __(1)__, which contains direction to open a breaker to fail 1RC-66 closed.

2) Assuming that no operator actions are taken, as steam leaks through the PORV, the flowrate of the steam is expected to __(2)__ because of Quench Tank pressure, over the long term.

Which ONE of the following completes the statements above?

A.

1. AP/02 (Excessive RCS Leakage)

2. continually lower B.

1. AP/02 (Excessive RCS Leakage)

2. lower then rise C.

1. AP/44 (Abnormal Pressurizer Pressure Control)

2. continually lower D.

1. AP/44 (Abnormal Pressurizer Pressure Control)

2. lower then rise Page 2 of 100

Question:

(1 point) 3 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 0500 Reactor Trip from 100%

SBLOCA has occurred Rule 2 (Loss of SCM) in progress 1A and 1B MD EFDWPs are operating Time = 0520 Rule 7 (SG Feed Control) in progress RCS temperature = 470°F slowly lowering EFW flow = 100 gpm to each SG 1A and 1B SG levels = 120 inches XSUR stable

1) At 0500, in accordance with Rule 2, __(1)__ gpm EFDW flow will initially be established to each SG.

2) At 0520, in accordance with Rule 7 (SG Feed Control), EFDW flow should be

__(2)__.

Which ONE of the following completes the statements above?

A.

1. 300

2. lowered B.

1. 300

2. raised C.

1. 450

2. lowered D.

1. 450

2. raised Page 3 of 100

Question:

(1 point) 4 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor trip from 100% power RCS pressure = 88 psig lowering Reactor Building pressure = 27 psig rising 1B LPI Pump failed to start Based on the above conditions, which ONE of the following describes the guidance provided in EOP Enclosure 5.1 (ES Actuation) regarding the LPI pumps and system operation?

EOP Enclosure 5.1 (ES Actuation)

A.

directs continued operation with only the 1A LPI pump and no re-alignment of LPI header flows.

B.

directs continued operation with only the 1A LPI pump and manually re-aligns LPI flow down both the 1A and 1B LPI headers.

C.

utilizes the 1A and the 1C LPI Pump and aligns flow down both headers with 1LP-9 and 10 closed.

D.

utilizes only the 1C LPI Pump and aligns flow down both headers with 1LP-9 &

10 open.

Page 4 of 100

Question:

(1 point) 5 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Unit 3 initial conditions:

Reactor Power = 100% stable 3A1 RCP Spool Piece vibration = 4 mils slowly rising Current conditions:

Reactor Power = 100% stable 3SA-9/E2 (RC PUMP VIBRATION EMERG HIGH) actuates 3A1 RCP Spool Piece vibration = 22 mils slowly rising Based on the current conditions above, which ONE of the following describes how the OATC and BOP will respond to mitigate this event?

The OATC will A.

perform a rapid power reduction to <70% and then the BOP will manually trip the 3A1 RCP.

B.

perform a rapid power reduction to <65% and then the BOP will manually trip the 3A1 RCP.

C.

manually trip the reactor and then perform IMAs; the BOP will manually trip the 3A1 RCP and then perform a symptom check.

D.

manually trip the reactor and then perform IMAs; the BOP will perform a symptom check and then manually trip the 3A1 RCP.

Page 5 of 100

Question:

(1 point) 6 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 70% stable Pressurizer level = 210 inches slowly lowering 1HP-120 (RC VOLUME CONTROL) failed closed AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection) initiated In accordance with AP/14

1) RCS makeup is initially provided by throttling __(1)__.

2) Pressurizer level is maintained at a MINIMUM of __(2)__ inches.

Which ONE of the following completes the statements above?

A.

1. 1HP-26 (1A HP INJ)

2. 200 B.

1. 1HP-26 (1A HP INJ)

2. 80 C.

1. 1HP-122 (RC Volume Control Bypass)

2. 200 D.

1. 1HP-122 (RC Volume Control Bypass)

2. 80 Page 6 of 100

Question:

(1 point) 7 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 1000:

U1 is in MODE 6 Reactor vessel refueled with the head installed LPI operating in Normal Mode per OP/1/A/1104/004, Low Pressure Injection System 1A LPI Pump is in service Purification is NOT in service RCP 1B1 seal replacement is in progress o PZR Level: 66 inches stable o 1LT-5 = 81 inches stable o RCP seal is removed Time = 1010:

1LP-12 (1A LPI Cooler Outlet) fails CLOSED.

o Crew entered AP/26 (Loss of Decay Heat Removal), due to degraded LPI flow and rising RCS temperature Which ONE of the following completes both statements in accordance with AP/26?

1) At Time = 1000, __(1)__ LPI Cooler(s) was/were in service.

2) At Time = 1010, the 1A LPI Pump __(2)__ required to be stopped.

A.

1. only one

2. is B.

1. only one

2. is NOT C.

1. two

2. is D.

1. two

2. is NOT Page 7 of 100

Question:

(1 point) 8 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 1030:

Reactor power = 100%

Component Cooling Return Flow = 583 gpm and lowering 1SA-09/C-1 (Component Cooling Return Flow Low) actuates Time = 1032:

Component Cooling Return Flow = 470 gpm and lowering The Standby CC pump is in AUTO but has NOT started CC Surge Tank level = 11 inches and lowering

1) At Time = 1030, Statalarm 1SA-09/C-1 __(1)__ valid.

2) At Time = 1032, 1SA-09/C-1 ARG __(2)__ direct manually starting the Standby CC pump.

Which ONE of the following completes the statements above?

A.

1. is

2. will B.

1. is

2. will NOT C.

1. is NOT

2. will D.

1. is NOT

2. will NOT Page 8 of 100

Question:

(1 point) 9 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:

Initial conditions:

Unit startup in progress RCS temperature = 310°F slowly rising Maintenance in progress in the area of 2DIB panelboard Current conditions:

2DIB breaker #24 (2RC-66 Pilot Valve DC solenoid power supply) is inadvertently opened Based upon the given conditions;

1) TS LCO __(1)__ is NOT met.

2) the position of 2RC-66 is __(2)__.

A.

1. 3.4.9 (Pressurizer)

2. Open B.

1. 3.4.9 (Pressurizer)

2. Closed C.

1. 3.4.12 (LTOP)

2. Open D.

1. 3.4.12 (LTOP)

2. Closed Page 9 of 100

Question:

(1 point) 10 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

Reactor trip due to Main Turbine trip CRD breakers opened Two control rods stuck at 30% withdrawn Reactor power = 7% and stable Rule 1, ATWS/Unanticipated Nuclear Power Production, is in progress Which ONE of the following describes the actions required to mitigate this event and the reason for those actions?

A.

Control FDW manually until Thot stabilizes to match core heat output.

B.

Ensure 2HP-5, Letdown Isolation, is closed to conserve RCS inventory.

C.

Manually drive ALL control rods to their in-limit to ensure 1% k/k shutdown margin.

D.

Borate the RCS by aligning the BWST to the HPI suction to add negative reactivity.

Page 10 of 100

Question:

(1 point) 11 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Steam Generator Tube Rupture in 1B SG Tcold = 490°F slowly lowering RB pressure = 3.1 psig slowly lowering RB temperature = 203°F slowly lowering 1B SG pressure = 606 psig slowly lowering 1B SG Full Range level = 54% slowly rising

1) 1B SG level __(1)__ reached the level at which water can enter the Main Steam lines.

2) Assuming 1B SG has reached the level where water enters the Main Steam line and steaming has been discontinued, the next procedural step per the SGTR tab is to __(2)__.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A.

1. has NOT

2. verify the 1A SG is available for steaming B.

1. has

2. verify the 1A SG is available for steaming C.

1. has NOT

2. align SG blowdown to the 1B SG to lower level D.

1. has

2. align SG blowdown to the 1B SG to lower level Page 11 of 100

Question:

(1 point) 12 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial Conditions:

Reactor trip from 100% power due to 1A MSLB Tcold lowered to 416oF Core SCM lowered to 0oF Current Conditions:

Tcold = 498oF and stable Core SCM = 78oF and stable Rule 2 (Loss of SCM) is complete 1A SG tube leakage = 5 gpm

1) __(1)__ was the EOP tab 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 12 of 100

Question:

(1 point) 13 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Initial conditions:

All three units Reactor power = 100%

Current conditions:

A Station Blackout occurs PSW Power is NOT available In accordance with the Blackout Tab, EOP Enclosure 5.32 (Load Shed of Inverters During SBO) is performed, which results in power being removed from __(1)__ in order to conserve the __(2)__ batteries.

Which ONE of the following completes the statement above?

A.

1. EFWPT Auxiliary Oil Pump

2. Power B.

1. EFWPT Auxiliary Oil Pump

2. Control C.

1. Diverse HPI/LPI

2. Power D.

1. Diverse HPI/LPI

2. Control Page 13 of 100

Question:

(1 point) 14 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following U1 conditions:

Initial conditions:

U1 tripped from 100% power due to a loss of offsite power Power was restored to the main feeder buses Forced Cooldown (FCD) Tab is in progress Plant Management has approved a Natural Circulation (NC) cooldown Current conditions:

NC cooldown has commenced Rx vessel head vents are open While conducting the NC cooldown, in accordance with the FCD Tab, __(1)__ SCM will be maintained > 150°F in order to __(2)__.

Which ONE of the following completes the statement above?

A.

1. Core

2. Keep the Rx vessel head from flashing B.

1. Core

2. Prevent voids in the tops of the hot legs C.

1. Loop

2. Keep the Rx vessel head from flashing D.

1. Loop

2. Prevent voids in the tops of the hot legs Page 14 of 100

Question:

(1 point) 15 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

A loss of both MFDW pumps occurs from 100% power Rule 3 (Loss of Main or Emergency FDW) is in progress 1FDW-315 and 1FDW-316 are maintaining SG levels at setpoint Current conditions:

1KVIB is de-energized Assuming no additional operator actions, which ONE of the following will be directed by the EOP?

A.

Take manual control of 1FDW-316 B.

Take manual control of 1FDW-315 C.

Feed the 1A SG through 1FDW-35 D.

Feed the 1B SG through 1FDW-44 Page 15 of 100

Question:

(1 point) 16 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 1300:

Reactor power = 65%

1LPSW-6 (UNIT 1 RCP COOLERS SUPPLY) fails closed Time = 1305:

AP/16 (Abnormal RCP Operation) in progress RCP Temperatures:

1A1 1A2 1B1 1B2 Radial Bearing Temperature 221°F 219°F 217°F 229°F Seal Return Temperature 252°F 197°F 189°F 202°F At Time = 1305, which ONE of the following is required per AP/16 Enclosure 5.1, RCP Immediate Trip Criteria?

A.

Manually trip the reactor and stop ALL RCPs B.

Manually trip the Reactor and stop RCPs 1A1 & 1B2 ONLY C.

Stop RCP 1A1 ONLY and verify FDW re-ratios properly D.

Stop RCP 1B2 ONLY and verify FDW re-ratios properly Page 16 of 100

Question:

(1 point) 17 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

Instrument Air pressure = 84 psig slowly lowering Aux IA pressure = 78 psig lowering AP/1/A/1700/22 (Loss of Instrument Air) initiated Which ONE of the following describes the actions required in accordance with AP/22 for the current conditions?

A.

Isolate RB Aux Coolers B.

Bypass HPI Purification Demineralizer C.

Dispatch an operator to manually open 1CC-8 D.

MANUALLY Trip the Reactor then trip BOTH Main FDW pumps Page 17 of 100

Question:

(1 point) 18 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 Conditions:

Initial Conditions:

Reactor Power 100%

TDEFWP isolated for repair Current Conditions:

Both Main Feedwater pumps trip 1A and 1B MDEFWPs fail NO Feedwater is available to the SGs (Main, Emergency, CBP, PSW)

Which ONE of the following describes

1) the next method of decay heat removal directed by the EOP?

2) a criterion used to determine when this method of decay heat removal is required?

A.

1. Initiate HPI forced cooling

2. PZR level = 375 inches B.

1. Initiate HPI forced cooling

2. BOTH SGs = 15 SU level C.

1. Feed SGs with SSF ASW

2. PZR level = 375 inches D.

1. Feed SGs with SSF ASW

2. BOTH SGs = 15 SU level Page 18 of 100

Question:

(1 point) 19 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Unit 1 initial conditions:

Reactor power = 68% stable 1B2 RCP secured Control Rod Group 7 position = 65% withdrawn Current conditions Control Rod Group 7 Rod 1 drops to 40% withdrawn Based on the above conditions

1) the CRD system __(1)__ generate an ICS runback.

2) the MAXIMUM final power level (Core Thermal Power) directed by AP/1 (Unit Runback) is __(2)__.

Which ONE of the following completes the statements above?

A.

1. will

2. < 60%

B.

1. will

2. < 45%

C.

1. will NOT

2. < 60%

D.

1. will NOT

2. < 45%

Page 19 of 100

Question:

(1 point) 20 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 50%

1KI Panelboard is de-energized for maintenance Current conditions:

Crew has entered AP/42 (Inadvertent ES Actuation)

An uncontrolled Tave decrease to outside the control band has occurred In accordance with AP/42 Step 4.22, the crew initiates AP/39 (Unintentional Boration)

AP/39 will FIRST direct restoration of Tave by _____.

Which ONE of the following completes the statements above?

A.

lowering CTP demand setpoint B.

adjusting boron concentration C.

withdrawing control rods D.

adjusting FDW Page 20 of 100

Question:

(1 point) 21 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial Conditions:

Reactor in MODE 3 Current conditions:

1DIB inverter DC Input breaker trips The associated source range NI power will be restored using the _____.

Which ONE of the following completes the statement above?

A.

Static Transfer Switch B.

Manual Transfer Switch C.

Inverter Bypass Switches D.

ASCO Switch Page 21 of 100

Question:

(1 point) 22 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Unit Startup in progress per OP/1/A/1102/001 (Controlling Procedure for Unit Startup)

Reactor power has been stabilized at 0.03% power on Wide Range Indications Current conditions:

One wide range channel start-up rate has failed high at 7 dpm

1) An OUT INHIBIT of __(1)__ will occur.

2) Action to immediately suspend operations involving positive reactivity changes

__(2)__ required in accordance with TS 3.3.10 (Wide Range Neutron Flux).

Which ONE of the following completes the statement above?

A.

1. regulating rods ONLY

2. is B.

1. regulating rods ONLY

2. is NOT C.

1. ALL control rods

2. is D.

1. ALL control rods

2. is NOT Page 22 of 100

Question:

(1 point) 23 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions:

Reactor is in MODE 6 Core offload in progress MP/0/A/1500/029, Reactor Bridge Operation, is in progress Reactor Fuel Bridge is withdrawing a fuel assembly that appears to be binding

1) The __(1)__ interlock will stop the withdrawal of the fuel assembly to prevent fuel damage.

2) The setpoint for this interlock is __(2)__.

Which ONE of the following correctly completes the statements above?

A.

1. Overload

2. 1750 lb B.

1. Overload

2. 2500 lb C.

1. Hoist

2. 1750 lb D.

1. Hoist

2. 2500 lb Page 23 of 100

Question:

(1 point) 24 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

An automatic reactor trip occurred from 100% power RCS pressure = 1000 psig lowering Rule 2 is in progress ES Channels 1 and 2 have actuated o HPI Flow Train A = 604 gpm stable o HPI Flow Train B = 0 gpm stable Current conditions:

HPI Flow Train A = 414 gpm stable Seal Injection Flow = 32 gpm stable HPI Crossover header flow = 476 gpm stable 1SA-18/D-6 (RC System Approaching Saturation Conditions) actuated o Loop A SCM = negative 2°F o Core SCM = 0°F

1) For the current plant conditions, HPI Flow __(1)__ within the limits of Rule 6.

2) The ICC Tab __(2)__ required to be entered.

Which ONE of the following completes both 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 24 of 100

Question:

(1 point) 25 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 90%

Tc ICS Station is in Hand 1B1 Reactor Coolant Pump shaft shears Based on the above conditions

1) the ICS system will initiate a plant runback at __(1)__ %/min.

2) once the transient stabilizes, loop A Tc will be __(2)__ loop B Tc.

A.

1. 25

2. approximately the same as B.

1. 20

2. approximately the same as C.

1. 25

2. higher than D.

1. 20

2. higher than Page 25 of 100

Question:

(1 point) 26 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

Main Turbine has tripped Rule 1 (ATWS/UNPP) in progress 3HP-24 will NOT open Reactor power = 3% and lowering SCM = 48 °F and rising Pzr level = 230 and rising The CRS has requested to be notified when HPI throttling criteria is met.

1) In accordance with Rule 6 (HPI Throttling Limits), HPI __(1)__ be throttled.

2) If/When throttling HPI in accordance with Rule 6 (HPI Throttling Limits) __(2)__.

Which ONE of the following completes the statements above?

A.

1. may

2. HPI pump operation is limited to two HPIPs B.

1. may NOT

2. HPI pump operation is limited to two HPIPs C.

1. may

2. total HPI flow must be throttled < 950 gpm including seal injection D.

1. may NOT

2. total HPI flow must be throttled < 950 gpm including seal injection Page 26 of 100

Question:

(1 point) 27 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

A LOCA has occurred The LOCA CD tab is in progress Core SCM = 0°F Pressurizer Level is rising All WR NIs <1%

1B HPI Header flow = 470 gpm

1) In accordance with Rule 6 (HPI), 1HP-27 (1B HP INJECTION) __(1)__ be throttled.

2) If HPI flow to the B Injection Header was through 1HP-409 (1HP-27 Bypass),

1SA-02/E-3 (HP LOOP B INJECTION FLOW HIGH) __(2)__ detect a high flow condition.

Which ONE of the following completes the statements above?

A.

1. must

2. would B.

1. must

2. would NOT C.

1. is NOT allowed to

2. would D.

1. is NOT allowed to

2. would NOT Page 27 of 100

Question:

(1 point) 28 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions:

Initial conditions:

Reactor power = 100%

CT-3 Lockout occurs Current conditions Reactor trip MFB re-energized 6900V power still unavailable HPI system leak downstream of 3HP-31 occurs 3A1 RCP SI flow = 3.9 gpm slowly lowering 3A2 RCP SI flow = 3.7 gpm slowly lowering 3B1 RCP SI flow = 3.5 gpm slowly lowering 3B2 RCP SI flow = 3.4 gpm slowly lowering Seal Inlet Header Flow = 40 gpm stable Assume no operator action Two minutes later, which ONE of the following describes the status of the following RCP support systems valve(s)?

A.

ONLY 3HP-21 has closed B.

ONLY 3HP-21 AND 3HP-31 have closed C.

ONLY ALL individual seal return valves and 3HP-21 have closed D.

ALL individual seal return valves, 3HP-21, and 3HP-31 have closed Page 28 of 100

Question:

(1 point) 29 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

1LPSW-6 (RCP MTR COOLERS SUPPLY) fails closed Which ONE of the following is the RCP Motor Stator MINIMUM temperature (ºF) that would require immediately tripping the RCP in accordance with AP/16 (Abnormal Reactor Coolant Pump Operation)?

A.

195 B.

225 C.

260 D.

300 Page 29 of 100

Question:

(1 point) 30 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 70%

ICS in automatic Operators perform an RCS deboration in accordance with OP/1/A/1103/004 C,.2 (Unit 1 Deborating IX for RCS Deboration (Rx At Power))

Current conditions:

Operators observe that final control rod position is higher than expected The potential cause for the observed plant response is _____.

Which ONE of the following completes the statement above?

A.

higher than anticipated letdown flow B.

higher than anticipated temperature through the resin C.

lower than anticipated temperature through the resin D.

higher than anticipated IX influent pH level Page 30 of 100

Question:

(1 point) 31 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 20% stable 1A and 1B SG Levels = 25 inches stable Current conditions:

1SA-02/E-8 (STM GEN A LEVEL LOW LIMIT) alarm actuates 1B SG Level = 25 inches stable

1) While 1A SG water level is being raised, reactor coolant makeup flow through 1HP-120, under the current conditions is expected to be __(1)__ than the makeup flowrate under the initial conditions.

2) The clearing of 1SA-02/E-8 is dependent upon 1A __(2)__ recovery.

Which ONE of the following completes the statement above?

A.

1. higher

2. SG Level and Loop Tave B.

1. higher

2. SG Level ONLY C.

1. lower

2. SG Level and Loop Tave D.

1. lower

2. SG Level ONLY Page 31 of 100

Question:

(1 point) 32 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Unit 1 is defueled LPI System is NOT in operation BWST in Purification Current conditions:

Chemistry reports BWST Boron Concentration = 2300 ppm The crew is preparing to fill the LPI system per OP/1/A/1104/004B Enclosure 4.3 (LPI System Fill from BWST and S/U After Defuel Maintenance) in preparation for refueling

1) BWST Purification is __(1)__ to remain in service while Enclosure 4.3 is implemented.

2) In accordance with OP/1/A/1502/007 Enclosure 4.1 (Refueling Prerequisites),

BWST Boron Concentration __(2)__ acceptable.

Which ONE of the following answers the statements above?

A.

1. required

2. is B.

1. required

2. is NOT C.

1. not allowed

2. is D.

1. not allowed

2. is NOT Page 32 of 100

Question:

(1 point) 33 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:

LOCA CD Tab in progress ALL RCPs running ALL SCMs = 4°F rising Pressurizer level is 100 inches stable Statalarm, 2SA-07/E-6, ES LPI BYPASS PERMIT actuated

1) The RCS pressure setpoint which will cause Statalarm 2SA-07/E-6 to actuate is

__(1)__ psig.

2) LPI is __(2)__ to be manually bypassed at this time.

Which ONE of the following completes the statements above?

A.

1. 865

2. NOT allowed B.

1. 865

2. required C.

1. 890

2. NOT allowed D.

1. 890

2. required Page 33 of 100

Question:

(1 point) 34 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

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 Component Drain Pump __(2)__ automatically trip once Quench Tank Level reaches 80 inches.

Which ONE of the following completes the statements above?

A.

1. 90

2. will B.

1. 90

2. will NOT C.

1. 100

2. will D.

1. 100

2. will NOT Page 34 of 100

Question:

(1 point) 35 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

1A CC Pump is in ON and is running 1B CC Pump is in AUTO and is off Current conditions:

The air supply to 1CC-8 completely severs An operator has been dispatched to manually re-position 1CC-8 Concerning the CC pumps

1) 30 seconds after 1CC-8 repositions due to the failure, __(1)__ pump will be running.

2) after 1CC-8 is manually placed back to its original position before the air supply failure __(2)__ CC pump(s) will be running.

Which ONE of the following completes the statements above?

A.

1. neither

2. the 1A & 1B B.

1. neither

2. only the 1A C.

1. the 1A

2. the 1A & 1B D.

1. the 1A

2. only the 1A Page 35 of 100

Question:

(1 point) 36 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

Loss of ALL feedwater occurs

1) The MINIMUM RCS pressure (psig) at which Quench Tank level would begin to RISE is __(1)__ psig.

2) The MINIMUM Quench Tank Pressure (psig) at which Containment pressure would begin to RISE is __(2)__ psig.

Which ONE of the following completes the statements above?

A.

1. 2450

2. 49 B.

1. 2450

2. 55 C.

1. 2500

2. 49 D.

1. 2500

2. 55 Page 36 of 100

Question:

(1 point) 37 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following U1 conditions:

Initial conditions:

Reactor power = 100%

Loss of all Main and Emergency Feedwater pumps occurs Current conditions:

Rule 3 is in progress at the step to manually throttle TBVs RCS temperature = 560°F rising RCS pressure = 2300 psig rising SCM > 0°F Which ONE of the following identifies the next action that the operating crew will perform?

A.

Initiation of HPI Forced Cooling B.

Feed SGs with Condensate Booster Pump C.

Secure all but one RCP due to RCS Pressure D.

Secure all RCPs to reduce heat input into the RCS Page 37 of 100

Question:

(1 point) 38 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

2TA and 2TB lockout Reactor power = 1% and lowering Two Group 2 control rods = 100% withdrawn The remaining control rods are fully inserted CRD Breakers A thru D are closed

1) RPS __(1)__ trip the reactor.

2) EP/2/A/1800/001 IMAs and Subsequent Actions requires the operator to __(2)__.

Which ONE of the following completes the statements above?

A.

1. did

2. OPEN 600 V CRD Breakers B.

1. did NOT

2. OPEN 600 V CRD Breakers C.

1. did

2. OPEN 2HP-26 and 2HP-27 D.

1. did NOT

2. OPEN 2HP-26 and 2HP-27 Page 38 of 100

Question:

(1 point) 39 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:

Initial conditions:

MDEFWPs = AUTO 2 Position Both Main FDW Pumps tripped from 100% power 2A and 2B SG XSUR Levels = 100 inches and lowering Current conditions:

The common airline to 2FDW-316 valve actuator is completely severed

1) IF NO operator action is taken for 15 minutes, the 2B SG XSUR level will

__(1)__.

2) The required operator action to control 2B SG level is performed __(2)__.

Which ONE of the following completes both statements above?

A.

1. still be lowering

2. in the control room by aligning valves and throttling 2FDW-44 B.

1. still be lowering

2. locally in the plant by throttling 2FDW-316 C.

1. be rising

2. in the control room by aligning valves and throttling 2FDW-44 D.

1. be rising

2. locally in the plant by throttling 2FDW-316 Page 39 of 100

Question:

(1 point) 40 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

RBCUs running in HIGH speed A Component Cooling (CC) system leak inside the RB caused a loss of CC cooling to the Control Rod Drive (CRD) units Operators entered AP/1/A/1700/20 (Loss of Component Cooling)

Based on the current conditions, AP/20 states that if CRD stator cooling is lost, stator temperatures will reach a trip value in approximately ______.

Which ONE of the following completes the statement above?

A.

4 minutes B.

30 minutes C.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D.

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Page 40 of 100

Question:

(1 point) 41 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following U3 conditions:

Initial conditions:

A large seismic event has caused multiple equipment failures 3TD switchgear locked out and remains de-energized LBLOCA is in progress RB Pressure = 8.5 psig rising Current conditions:

ES Channel 8 automatically actuates ES Channel 7 fails to actuate Assuming no operator action

1) At least one RB Spray (RBS) pump __(1)__ automatically start.

2) At least one RBS discharge valve (3BS-1 or 3BS-2) __(2)__ automatically open.

Which ONE of the following completes the statements above?

A.

1. does

2. does B.

1. does

2. does NOT C.

1. does NOT

2. does D.

1. does NOT

2. does NOT Page 41 of 100

Question:

(1 point) 42 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions:

Reactor tripped from 100% power Steam pressure was lowered to reseat a lifting MS relief valve RCS temperature = 544oF slowly rising Based on the conditions above, which one of the following Turbine Master setpoint knob positions would result in stabilizing RCS temperature 544°F?

A.

995 psig B.

980 psig C.

930 psig D.

855 psig Page 42 of 100

Question:

(1 point) 43 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Unit 1 is reducing power for a refueling outage Reactor power = 5% and lowering 1A OTSG SUR level is 24 inches 1B OTSG SUR level is 26 inches The ICS system controlling input for the feedwater signal for the A SG is __(1)__ and for the B SG is __(2)__.

A.

1. Startup Level Error

2. Feedwater Flow Error B.

1. Startup Level Error

2. Startup Level Error C.

1. Feedwater Flow Error

2. Startup Level Error D.

1. Feedwater Flow Error

2. Feedwater Flow Error Page 43 of 100

Question:

(1 point) 44 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

ICS SG Master is in MANUAL Current conditions:

1FDW-11 (1B1 FDW Htr Inlet (3-Way)) has been inadvertently placed in BYPASS Which ONE of the following describes the Unit 1 plant response?

Assuming no operator response, Tc will be __(1)__ and the ICS system __(2)__

automatically compensate feedwater flow for the change in feedwater temperature.

A.

1. higher

2. will B.

1. higher

2. will not C.

1. the same

2. will D.

1. the same

2. will not Page 44 of 100

Question:

(1 point) 45 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 0400:

Reactor power = 100%

Both Main FDW pumps trip Time = 0403:

1A and 1B MDEFDW Pumps operating Power has been lost to the 1FDW-316 Moore Controller ONLY Which ONE of the following describes the response of 1B SG level?

ASSUME NO OPERATOR ACTION A.

Decrease to dryout B.

Automatically controlled at 30 C.

Automatically controlled at 240 D.

Increase to overflow into the steam lines Page 45 of 100

Question:

(1 point) 46 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Unit 1 & 2 B LPSW Pump 4160 Volt AC electrical power is supplied from Switchgear ______.

Which ONE of the following completes the statement above?

A.

1TC only B.

2TC only C.

1TD only D.

1TD or 2TD Page 46 of 100

Question:

(1 point) 47 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

1DCA and 1DCB Bus tie circuit breakers are in their normal position

1) 1DIB Panelboard is receiving one source of auctioneered DC power from

__(1)__ Bus.

2) 1DIB Panelboard is receiving another source of auctioneered DC power from

__(2)__ Bus.

Which ONE of the following completes the statements above?

A.

1. 1DCA

2. 2DCB B.

1. 1DCA

2. 3DCB C.

1. 1DCB

2. 2DCB D.

1. 1DCB

2. 3DCB Page 47 of 100

Question:

(1 point) 48 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Time = 1400 All three units at 100% power Unit 3 125V I&C Vital DC system has a ground on the P-leg Time = 1420 Units 1, 2, and 3 DC busses have been isolated per ARG actions At Time = 1420, the magnitude of the ground _____.

Which ONE of the following completes the statement above?

A.

can NOT be assessed on any Units Operator Aid Computer B.

can be assessed on ONLY the Unit 1 Operator Aid Computer C.

can be assessed on ONLY the Unit 3 Operator Aid Computer D.

can be assessed on ANY Units Operator Aid Computer Page 48 of 100

Question:

(1 point) 49 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

ACB-4 closed A Switchyard Isolation occurs Current conditions:

Keowee Unit 2 Emergency lockout 230 KV Yellow Bus Differential lockout Main Feeder buses will be energized __(1)__ from __(2)__.

Which ONE of the following completes the statements above?

A.

1. manually

2. CT-4 B.

1. automatically

2. CT-4 C.

1. manually

2. CT-5 D.

1. automatically

2. CT-5 Page 49 of 100

Question:

(1 point) 50 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 plant 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 1SA-15 D-4, EL LOAD SHED CHNL A LOGIC INITIATE, is in alarm 1SA-15 A-6, LOAD SHED INCOMPLETE, is in alarm LOAD SHED COMPLETE is not indicated on any ES Channel Two Hotwell Pumps (HWPs) remain operating

1) In accordance with AP/11, operators are required to __(1)__.

2) This action is required to __(2)__.

Which ONE of the following completes the statements above?

A.

1. place all HWPs to OFF

2. ensure CT-4 is not overloaded B.

1. place all HWPs to OFF

2. ensure adequate voltage is available for ES components C.

1. reduce HWPs to only one HWP operating with one shutdown HWP in AUTO

2. ensure CT-4 is not overloaded D.

1. reduce HWPs to only one HWP operating with one shutdown HWP in AUTO

2. ensure adequate voltage is available for ES components Page 50 of 100

Question:

(1 point) 51 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

At time: 1200 Reactor Power = 45%

1A Steam Generator tube leak of 5.1 gpd RCS activity = 0.25 µCi/ml DEI rising At time: 1400 Reactor Power = 45%

1A Steam Generator tube leak of 5.1 gpd RCS activity = 0.65 µCi/ml DEI rising

1) Between 1200 and 1400, 1RIA-16 indication will __(1)__.

2) At 1400 and in accordance with AP/31 (Primary to Secondary Leakage),

1RIA-59 __(2)__ be used to calculate SG tube leak size.

Which ONE of the following completes the statements above?

A.

1. rise

2. will B.

1. rise

2. will NOT C.

1. stay the same

2. will D.

1. stay the same

2. will NOT Page 51 of 100

Question:

(1 point) 52 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

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

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

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

Which ONE of the following completes the statements above?

A.

1. 140

2. remain unchanged B.

1. 140

2. rise C.

1. 180

2. remain unchanged D.

1. 180

2. rise Page 52 of 100

Question:

(1 point) 53 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

Which ONE of the following describes an effect of a loss of LPSW?

A.

In a subsequent LOCA, RCS cooling would be reduced during the recirculation phase B.

In a subsequent LOHT, the TDEFDW pump would overheat C.

The Primary IA Compressor would overheat D.

The HPI pump motors would overheat Page 53 of 100

Question:

(1 point) 54 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Unit 2 initial conditions:

Reactor power = 100%

IA pressure = 95 psig slowly lowering Current conditions:

IA pressure = 60 psig slowly lowering Based on the above conditions, which ONE of the following describes status of the Main and Startup FDW control valves?

A.

2FDW-35 and 44 (Startup FDW Control Valves) have failed closed and 2FDW-32 and 41 (Main FDW Control Valves) are controlling Main FDW flow.

B.

2FDW-35 and 44 (Startup FDW Control Valves) and 2FDW-32 and 41 (Main FDW Control Valves) have failed CLOSED.

C.

2FDW-35 and 44 (Startup FDW Control Valves) and 2FDW-32 and 41 (Main FDW Control Valves) have failed OPEN.

D.

2FDW-35 and 44 (Startup FDW Control Valves) and 2FDW-32 and 41 (Main FDW Control Valves) have failed as is.

Page 54 of 100

Question:

(1 point) 55 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 1200 Reactor in MODE 5 RCS Loops dropped Pressurizer level = 340 inches stable RB Cavity washdown in progress RB Purge in progress Reactor Building Sump is being pumped Time = 1205 Pressurizer level 322 inches lowering 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 is required to 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 55 of 100

Question:

(1 point) 56 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Startup in progress in accordance with OP/1/A/1102/001 Enclosure 4.7, Unit Startup from 532ºF/2155 psig to MODE 1

1) A Control Rod Out Inhibit will be received if Startup Rate exceeds __(1)__ DPM on one Wide Range (WR) channel.

2) A Control Rod Out Inhibit __(2)__ be generated when a Source Range (SR) nuclear instrument instantaneously fails high.

Which ONE of the following correctly completes the statement above?

A.

1. 1

2. will B.

1. 2

2. will C.

1. 1

2. will NOT D.

1. 2

2. will NOT Page 56 of 100

Question:

(1 point) 57 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 0400 Reactor trip from 100% power due to a loss of offsite power Forced Cooldown (FCD) tab in progress Tcold = 550ºF stable Time = 0500 RCS pressure = 2155 psig stable A Natural Circulation cooldown is initiated 1RC-160 (RX Vessel Head Vent) is open 1RC-159 (RX Vessel Head Vent) will NOT open

1) At 0400 and in accordance with the FCD tab, the MAXIMUM allowable cooldown rate is __(1)__.

2) During the cooldown, Reactor Vessel head voids __(2)__ expected to occur.

Which ONE of the following completes the statements above?

A.

1. <50°F/hr

2. are B.

1. <50°F/hr

2. are NOT C.

1. <50°F/1/2 hr

2. are D.

1. <50°F/1/2 hr

2. are NOT Page 57 of 100

Question:

(1 point) 58 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 0900:

Reactor startup in progress Wide Range (WR) NI power = 4E-3% and rising Time = 0905:

All WR NIs are declared INOPERABLE In accordance with TS 3.3.10 (Wide Range Neutron Flux)

1) At Time = 0905, __(1)__ wide range neutron flux channels are required to be OPERABLE.

2) The CRD trip breakers are required to be opened __(2)__.

Which ONE of the following completes the statements above?

A.

1. 2 (two)

2. immediately B.

1. 3 (three)

2. immediately C.

1. 2 (two)

2. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D.

1. 3 (three)

2. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 58 of 100

Question:

(1 point) 59 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 0400:

Reactor power = 100%

An ICCM Train B qualified CETC develops an open circuit in the detector Time = 0430:

Core SCM = 0°F RB pressure = 8 psig

1) At 0400, this CETC __(1)__ be used in ICCM Train B Core SCM calculation.

2) At 0430, __(2)__ CETCs will be used in ICCM Train B Core SCM calculation.

Which ONE of the following completes the statements above?

A.

1. will

2. 5 B.

1. will

2. 4 C.

1. will NOT

2. 5 D.

1. will NOT

2. 4 Page 59 of 100

Question:

(1 point) 60 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Which ONE of the following are the electrical power supplies to the Penetration Room Ventilation (PRV) Fans?

PRV Fan A PRV Fan B A.

XS1 XS2 B.

XS2 XS1 C.

XS4 XS5 D.

XS5 XS4 Page 60 of 100

Question:

(1 point) 61 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

Which ONE of the following will result in an AUTOMATIC trip of the Main Turbine?

A.

EHC header pressure 1150 psig B.

High Moisture Separator Reheater level on one level switch on two of four MSRHs C.

780 psig discharge pressure on BOTH Main Feedwater pumps D.

72 psig hydraulic oil pressure on BOTH Main Feedwater pumps Page 61 of 100

Question:

(1 point) 62 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 80%

1A HWP is being investigated by Maintenance due to lower than normal discharge pressure Current conditions:

1B HWP spuriously trips Condensate Booster Pump suction pressure lowers to 13 psig A runback is in progress Based upon current plant conditions, and in accordance with AP/01 (Unit Runback)

1) The runback will continue until __(1)__.

2) Enclosure 5.1 (Control of Plant Equipment during Runback) will direct the operators to __(2)__.

Which ONE of the following completes the statements above?

A.

1. 15% rated power

2. secure the E Heater Drain Pumps B.

1. 15% rated power

2. maintain Pressurizer level between 200 and 220 inches C.

1. >16 psig CBP suction pressure

2. secure the E Heater Drain Pumps D.

1. >16 psig CBP suction pressure

2. maintain Pressurizer level between 200 and 220 inches Page 62 of 100

Question:

(1 point) 63 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Time = 16:05:00 All 3 Units Reactor power = 100%

A and B LPSW pumps operating Switchyard Isolate occurs Time = 16:05:30 Unit 1&2 MFB 1 & 2 re-energized

1) A and B LPSW pumps restarted at Time = __(1)__.

2) Unit 1 & 2 LPSW is supplied via the ECCW __(2) siphon flowpath.

Which ONE of the following completes the statements above?

A.

1. 16:05:40

2. first B.

1. 16:05:40

2. second C.

1. 16:05:30

2. first D.

1. 16:05:30

2. second Page 63 of 100

Question:

(1 point) 64 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

IA header pressure = 88 psig lowering The Diesel Air Compressors are __(1)__ and SA-141 (SA to IA Controller) is __(2)__.

Which ONE of the following completes the statement above?

A.

1. Operating

2. Open B.

1. Operating

2. Closed C.

1. Shutdown

2. Open D.

1. Shutdown

2. Closed Page 64 of 100

Question:

(1 point) 65 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

1SA-3/B-6 (FIRE ALARM) comes into alarm The Fire Brigade is using a fire hose to fight a fire in the U1 TB Basement

1) The Standby HPSW pump start when EWST level lowers to __(1)__ gallons.

2) The __(2)__ HPSW pump is normally aligned as the Standby pump.

Assume no operator actions taken by Control Room operators Which ONE of the following completes the statement above?

A.

1. 50,000

2. A B.

1. 60,000

2. A C.

1. 50,000

2. B D.

1. 60,000

2. B Page 65 of 100

Question:

(1 point) 66 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Unit 1 is operating at 100% power.

Which ONE of the following comparisons is allowed to complete the following step per PT/1/A/0600/001, Periodic Instrument Surveillance, Enclosure 13.1, Mode 1 & 2?

Step 1.3 Verify diverse power indications within +/- 2.0%.

A.

COMPARE the NI average TO the OAC Calculated Thermal Power Primary B.

COMPARE the OAC Calculated Thermal Power Primary TO the OAC Calculated Thermal Power T C.

COMPARE the OAC Calculated Thermal Power Best TO the OAC Calculated Thermal Power T D.

COMPARE each NI TO the NI average Page 66 of 100

Question:

(1 point) 67 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Time = 1000:

All three Oconee Units = 100% power Load Dispatch calls with a request to make a voltage adjustment Time = 1030:

The Shift Manager and other licensed operators participate in a conference call with other station departments to coordinate a previously-scheduled electrical bus outage that will begin later on this shift.

In accordance with section 5.1.3, (Log Entry Details and Accuracy), of procedure AD-OP-ALL-0112, (OPERATIONS LOG KEEPING AND CHART RECORDERS)

(1) the name of the individual load dispatch, or the name of the operator who received the call from the load dispatch, __(1)__ required to be included in the narrative log, AND (2) the conference call with other departments to coordinate the previously-scheduled electrical bus outage __(2)__ required to be included in the narrative log.

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 67 of 100

Question:

(1 point) 68 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor in MODE 6 RB Purge in progress Defueling in progress All four Source Range NIs are OPERABLE In accordance with MP/0/A/1500/009 (Defueling/Refueling Procedure)

1) a MINIMUM of __(1)__ Source Range NI(s) is/are required.

2) immediate suspension of fuel handling would be required if __(2)__.

Which ONE of the following completes the statements above?

A.

1. one

2. 1RIA-49 fails LOW B.

1. one

2. Fuel Transfer Canal water level is 21 feet lowering C.

1. two

2. 1RIA-49 fails LOW D.

1. two

2. Fuel Transfer Canal water level is 21 feet lowering Page 68 of 100

Question:

(1 point) 69 ILT21 ONS SRO NRC Examination Oconee Nuclear Station In accordance with AD-HU-ALL-0005 (HUMAN PERFORMANCE TOOLS), which ONE of the following describes

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

2) the minimum level of approval required?

NOTE: Assume the IV of a single valve requires 30 seconds to perform A.

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

2. Plant SRO B.

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

2. Plant SRO C.

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

2. Operations Superintendent D.

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

2. Operations Superintendent Page 69 of 100

Question:

(1 point) 70 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Unit startup in progress Turbine Generator startup is in progress using OP/1/A/1106/001 TURBINE GENERATOR, Enclosure 4.1 TURBINE GENERATOR STARTUP Selecting the Turbine Load pushbutton sends a signal to __(1)__ and is performed

__(2)__ paralleling to the grid.

Which ONE of the following completes the statement above?

A.

1. close the Turbine Bypass Valves which in turn, causes the Turbine Control Valves to open to maintain steam pressure constant

2. before B.

1. close the Turbine Bypass Valves which in turn, causes the Turbine Control Valves to open to maintain steam pressure constant

2. after C.

1. open the Turbine Control Valves which in turn, causes the Turbine Bypass Valves to close to maintain steam pressure constant

2. before D.

1. open the Turbine Control Valves which in turn, causes the Turbine Bypass Valves to close to maintain steam pressure constant

2. after Page 70 of 100

Question:

(1 point) 71 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Radiation Monitor Check (PT/0/A/0230/001) enclosure 13.7, RIA-45 setpoints for Unit 1&2 GWD tank release, is in progress The Unit 1&2 GWD tank release will be made at 2/3 of the station limit To reset the Alert Setpoint for 3RIA-45 in accordance with (PT/0/A/0230/001) enclosure 13.7,

1) Unit 3 RB purge __(1)__ required to be off.

2) GWD release on Unit 3 __(2)__ be in progress.

Which ONE of the following completes the statements above?

A.

1. is

2. can B.

1. is

2. can NOT C.

1. is NOT

2. can D.

1. is NOT

2. can NOT Page 71 of 100

Question:

(1 point) 72 ILT21 ONS SRO NRC Examination Oconee Nuclear Station In accordance with AD-EP-ALL-0205 (Emergency Exposure Controls), which one of the following completes the statement below?

To protect valuable property the MAXIMUM total effective dose equivalent (TEDE) exposure limit is _______ REM.

A.

5 B.

10 C.

15 D.

25 Page 72 of 100

Question:

(1 point) 73 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

Which ONE of the following would require entry into the EOP?

A.

Reactor power increases to 102%

B.

Group 2 Rod 6 Control Rod fully inserts into the core AND Group 2 Rod 5 slips 6% below Group 2 average height C.

Reactor Coolant System leakage in the RB of 55 gpm D.

Reactor Coolant System pressure increases to 2360 psig Page 73 of 100

Question:

(1 point) 74 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Initial conditions:

Units 1 and 3 are at 100% power Unit 2 is in Mode 5 with primary hand holes removed and the Fuel Transfer Canal NOT flooded Current conditions:

Security staff has informed the control room that a Code Red exists with Unit 2 being the affected unit In accordance with AP/0/A/1700/045, Site Security Threats, which two of the following are correct?

1) Ensure a licensed operator has been dispatched to the SSF with a respirator and flashlight, for each unit.

2) Ensure an operator from the Control Room has been dispatched to the Unit 2 LPI hatch area to immediately open LP-21/22

3) Ensure a licensed operator has been dispatched to the SSF for Units 1 and 3 ONLY with a respirator and flashlight

4) Ensure an operator from the Control Room has been dispatched to the Unit 2 LPI hatch area with a flashlight and radio to open LP-21/22 when directed A.

1 and 2 B.

3 and 2 C.

1 and 4 D.

3 and 4 Page 74 of 100

Question:

(1 point) 75 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

AP/0/A/1700/045 (Site Security Threats) has been entered and enclosure 5.1.A, Unit 1 Actions for Imminent Aircraft Threat are in progress The crew has tripped the Reactor, completed EOP IMAs and Symptoms check

1) Steam Generator level setpoints __(1)__ be controlled in accordance with AP/0/A/1700/045.

2) AP/0/A/1700/045 __(2)__ designated as proprietary information.

Which ONE of the following completes the statements above?

A.

1. will

2. is B.

1. will

2. is NOT C.

1. will NOT

2. is D.

1. will NOT

2. is NOT Page 75 of 100

Question:

(1 point) 76 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 1200 Reactor power = 100% stable AFIS bypassed for maintenance SA-16/C-1 (230 KV Swyd Isolate ES Permit) actuated 230 KV Yellow Bus voltage = 224.2 KV rising Time = 1201 AP/34 (Degraded Grid) in progress Main Turbine trips due to low grid frequency 230 KV Yellow Bus voltage = 226.8 KV rising RCS pressure = 1245 psig rapidly lowering RB pressure = 11.4 psig rapidly rising Tave = 545ºF slowly lowering At Time = 1201, Engineered Safeguards systems...

1) will be energized from __(1)__.

2) __(2)__ sufficient to maintain Reactor Building pressure within design limits.

Which ONE of the following completes the statements above?

A.

1. CT-1

2. are B.

1. CT-1

2. are NOT C.

1. CT-4

2. are D.

1. CT-4

2. are NOT Page 76 of 100

Question:

(1 point) 77 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

BOTH channels of AMSAC disabled Current conditions:

Both Main Feedwater Pumps Tripped Reactor power = 60% and slowly lowering

1) 1A MDEFWP, 1B MDEFWP AND the TDEFWP __(1)__ automatically start.

2) In accordance with B&W analysis, a MINIMUM of __(2)__ gallons per minute of Emergency Feedwater flow is required to limit the RCS pressure increase to below the design standard for this event.

Which ONE of the following completes the statements above?

A.

1. will

2. 750 B.

1. will NOT

2. 750 C.

1. will

2. 375 D.

1. will NOT

2. 375 Page 77 of 100

Question:

(1 point) 78 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 1200:

Reactor startup in progress Reactor power = 3% stable The operating Main Feedwater Pump trips Time = 1200:15 The SRO directs the OATC to perform IMAs Time = 1202:

Reactor power = 3% stable

1)

The reactor __(1)__ automatically trip at Time = 1200 when the operating FDW pump tripped.

2)

The SRO should __(2)__.

Which ONE of the following completes the statements above?

A.

1. should

2. perform actions in the Subsequent Actions tab to shut down the reactor B.

1. should

2. GO TO the UNPP tab to perform actions to shut down the reactor C.

1. should NOT

2. perform actions in the Subsequent Actions tab to shut down the reactor D.

1. should NOT

2. GO TO the UNPP tab to perform actions to shut down the reactor Page 78 of 100

Question:

(1 point) 79 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following U2 conditions:

Initial Conditions:

Unit 2 TDEFW pump is tagged out for bearing replacement A station blackout has occurred for all Oconee units Rule 3, Loss of Main or Emergency Feedwater is in progress PSW is unavailable Current Conditions:

Unit 2 RCS pressure is 2325 psig and rising No source of feedwater has been established for Unit 2 Two (2) Unit 2 Control Room Operators are available The SSF is available for ASW and RCMU In accordance with Unit 2 EOP Blackout Tab, the CRS for Unit 2 will direct which of the following actions?

A.

Perform Rule 4, HPI Forced Cooling B.

Re-perform Rule 3, Loss of Main or Emergency Feedwater C.

Perform EOP enclosure 5.38, Restoration of Power D.

Perform Unit 1 EOP enclosure 5.42, Alignment of Portable Pump to Feed SGs Page 79 of 100

Question:

(1 point) 80 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Time = 1100:

All three Oconee Units at 100% power 3KVIB panelboard de-energized Time = 1200:

1SA-13/E-7 (Power Panelboard 1DIC Voltage Low) is in alarm 1DIC panelboard is de-energized

1) At Time = 1100, the basis for the shorter completion time of TS 3.8.8 Condition F for KVIA or KVIB OOS is due to providing power for the __(1)__.

2) At Time = 1200, TS LCO 3.8.8 (Distribution Systems - Operating), is NOT met for __(2)__.

Which ONE of the following completes the statements above?

A.

1. digital Engineered Safeguards Protective System (ESPS) channels

2. Units 1 AND 3 ONLY B.

1. S, SK, and SL breakers, standby bus protective relaying, and retransfer to startup logic

2. Units 1 AND 3 ONLY C.

1. digital Engineered Safeguards Protective System (ESPS) channels

2. Units 1, 2, AND 3 D.

1. S, SK, and SL breakers, standby bus protective relaying, and retransfer to startup logic

2. Units 1, 2, AND 3 Page 80 of 100

Question:

(1 point) 81 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Time = 0800:

Reactor power = 50%

Unit 1 is supplying the AS header 1RC-66, (PORV) fails open 1RC-4, (PORV BLOCK) fails to close Time = 0810:

LOSCM tab is in progress HPI flow could only be established in the 1A header MD EFDW pumps FAIL to start TD EFDWP is supplying feedwater to both SGs Rapid SG depressurization has begun

1) Both SGs should be depressurized to 250 - 275 psig band because this will prevent __(1)__.

2) IF the RCS cooldown results in an increase in neutron flux, the CRS will

__(2)__.

Which ONE of the following completes the statements above?

A.

1. emptying the CFTs introducing nitrogen to the RCS

2. GO TO the UNPP tab B.

1. emptying the CFTs introducing nitrogen to the RCS

2. remain in the LOSCM C.

1. overcooling and exceeding SG Tube-to-Shell T limits

2. GO TO the UNPP tab D.

1. overcooling and exceeding SG Tube-to-Shell T limits

2. remain in the LOSCM Page 81 of 100

Question:

(1 point) 82 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following U1 conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

1A SG has a 165 gpd tube leak 1B SG has a 21 gpm tube leak

1) The reactor should be taken off line in accordance with __(1)__.

2) The TS 3.4.11 (RCS Specific Activity) Bases limit for primary to secondary leakage is based upon the safety analysis for a __(2)__ following a reactor trip from 100% reactor power in order to ensure the dose consequences are less than the limits in 10 CFR 100.

Which ONE of the following completes the statements above?

A.

1. SGTR Tab

2. stuck open MSRV B.

1. SGTR Tab

2. Steam Line Break accident C.

1. AP/31 (Primary to Secondary Leakage)

2. stuck open MSRV D.

1. AP/31 (Primary to Secondary Leakage)

2. Steam Line Break accident Page 82 of 100

Question:

(1 point) 83 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions:

Initial conditions:

A Challenging Fire which requires the evacuation of the Unit 3 Control Room is in progress Unit 3 has entered the following Abnormal Procedures:

o AP/0/A/1700/043 (Fire Brigade Response Procedure) o AP/0/A/1700/025 (Standby Shutdown Facility Emergency Operating Procedure) o AP/3/A/1700/050 (Challenging Plant Fire)

Current Conditions AP/50 Section 4G (Unit 3 Control Room Evacuation) is in progress o The crew has not yet left the control room

1) In accordance with AP/43, a Challenging Fire is defined as __(1)__.

2) Per AP/50 Enclosure 4G, the CRS is required to HOLD until AP/25 Enclosure __(2)__ is completed prior to directing the OATC to perform Enc 5.5 (OATC Actions for Control Room Evacuation) per Step 3.

Which ONE of the following completes the statements above?

A.

1. a fire in the plant that is NOT extinguished within 15 minutes of Control Room notification

2. 5.11 (SSF Breaker Transfer for Unit 3)

B.

1. a fire in the plant that is NOT extinguished within 15 minutes of Control Room notification

2. 5.15C (U3 OATC Actions for Fire)

C.

1. a fire that is burning cables (bundles/trays which have the potential to affect additional equipment)

2. 5.11 (SSF Breaker Transfer for Unit 3)

D.

1. a fire that is burning cables (bundles/trays which have the potential to affect additional equipment)

2. 5.15C (U3 OATC Actions for Fire)

Page 83 of 100

Question:

(1 point) 84 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Unit 2 has entered MODE 6, and operators are making preparations to begin core off-load Which ONE of the following completes the below statements in accordance with the BASES of Technical Specification LCO 3.9.3, Containment Penetrations?

(1) Placement of a temporary cover plate installed and sealed against the inner emergency air lock door flange gasket is an acceptable means for providing containment closure; __(1)__.

(2) Prior to beginning fuel handling operations, __(2)__ the requirement that the air lock be closed, which constitutes operability for this requirement.

A.

1. but all cables, hoses, or service air piping run through the temporary cover plate are required to be removed

2. a one-time leak test of the temporary cover plate over the emergency air lock is required to satisfy B.

1. but all cables, hoses, or service air piping run through the temporary cover plate are required to be removed

2. leak testing is NOT required; visual inspection of the temporary cover plate over the emergency air lock satisfies C.

1. as long as all cables, hoses, and/or service air piping run through the temporary cover plate sleeves are installed and sealed

2. a one-time leak test of the temporary cover plate over the emergency air lock is required to satisfy D.

1. as long as all cables, hoses, and/or service air piping run through the temporary cover plate sleeves are installed and sealed

2. leak testing is NOT required; visual inspection of the temporary cover plate over the emergency air lock satisfies Page 84 of 100

Question:

(1 point) 85 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Unit 1 plant conditions:

Reactor power = 100% stable RCS DEI = 0.5 µCi/gm stable AP/21 (High Activity in RCS) in progress Based on the above conditions, which ONE of the following correctly states:

1) whether AP/21 requires a power reduction to be initiated?

2) the procedure used by AP/21 to perform the power reduction when a shutdown is required?

A.

1. Initiation of power reduction NOT required

2. OP/1/A/1102/004 (Operation at Power)

B.

1. Initiation of power reduction NOT required

2. AP/29 (Rapid Unit Shutdown)

C.

1. Initiation of power reduction IS required

2. OP/1/A/1102/004 (Operation at Power)

D.

1. Initiation of power reduction IS required

2. AP/29 (Rapid Unit Shutdown)

Page 85 of 100

Question:

(1 point) 86 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Unit 1 plant conditions:

Reactor is in MODE 3 Startup is in progress 1B LPI Train flow instrument is found to be NOT operable Based on the conditions above, which one of the following completes the statements below in accordance with Technical Specifications Bases?

1) The operating crew is required to declare __(1)__ NOT operable.

2) Entry into MODE 2 __(2)__ permitted.

A.

1. 1B LPI Train ONLY

2. is B.

1. 1B LPI Train ONLY

2. is NOT C.

1. BOTH 1B LPI Train and 1B RBS Train

2. is D.

1. BOTH 1B LPI Train and 1B RBS Train

2. is NOT Page 86 of 100

Question:

(1 point) 87 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

OP/1/A/1103/002, (Filling and Venting RCS) Enclosure 4.14 (Establishing Pzr Steam Bubble and RCS Final Vent) in progress Quench Tank level = 84 inches Quench Tank pressure = 0.5 psig The Pressurizer is vented to the Quench Tank for 30 minutes Based on the above conditions, which ONE of the following describes:

1) QT pressure (psig) that would verify Pzr Steam Bubble Formation is complete?

2) actions required for entry into MODE 4 in accordance with Tech Specs if 1GWD-12 (QUENCH TANK VENT INSIDE RB) failed to close during system re-alignment following Pzr steam bubble formation?

REFERENCE PROVIDED A.

1. 0.6

2. allowed ONLY when 1GWD-12 is restored to OPERABLE B.

1. 0.6

2. allowed if 1GWD-13 (QUENCH TANK VENT OUTSIDE RB) is closed and de-activated C.

1. 2.5

2. allowed ONLY when 1GWD-12 is restored to OPERABLE D.

1. 2.5

2. allowed if 1GWD-13 (QUENCH TANK VENT OUTSIDE RB) is closed and de-activated Page 87 of 100

Question:

(1 point) 88 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

1B RPS Channel in MANUAL BYPASS Current conditions:

RC Loop A NR Press 1 (RPS Ch A) = 1790 psig RC Loop A NR Press 2 (RPS Ch B) = 2153 psig RC Loop B NR Press 1 (RPS Ch C) = 2156 psig RC Loop B NR Press 2 (RPS Ch D) = 2150 psig 1SA-01/A-2 (Channel A Lo Press Trip) actuates 1SA-01/A-5 (1A Var Lo Press Trip) actuates 1SA-05/A-5 (1A RPS Trouble) actuates

1) In accordance with Tech Spec 3.3.1, RPS Channel A Low RCS Pressure Trip function at this time is __(1)__.

2) In accordance with OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) RPS Channel A __(2)__.

Which ONE of the following completes the statements above?

A.

1. operable

2. must be placed in trip with the key switch B.

1. NOT operable

2. must be placed in trip with the key switch C.

1. operable

2. is unaffected due to the 2.min actuation logic D.

1. NOT operable

2. is unaffected due to the 2.min actuation logic Page 88 of 100

Question:

(1 point) 89 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Time = 2100 on June 1, 2020:

Unit 2 Reactor power = 100%

The 2A Reactor Building Spray (RBS) pump is declared INOPERABLE and Unit 2 enters the appropriate CONDITION(s) of Technical Specification (TS)

LCO 3.6.5, Reactor Building Spray and Cooling Systems Time = 1400 on June 3, 2020:

The 2C Reactor Building Cooling Unit (RBCU) is declared INOPERABLE and Unit 2 enters the appropriate CONDITION(s) of LCO 3.6.5 Current Conditions at Time = 1800 on June 6, 2020:

You are the oncoming Unit 2 SRO after several weeks of leave Both the 2A RBS pump and the 2C RBCU have remained INOPERABLE All other RBS and RBCU components have been and are OPERABLE Unit 2 has complied with all applicable LCO 3.6.5 REQUIRED ACTIONS and COMPLETION TIMES Based on the current conditions, which ONE of the following was/is the correct application of TS LCO 3.6.5?

REFERENCE PROVIDED A.

Unit 2 is simultaneously in CONDITIONs A and B. LCO 3.6.5 allows continued operation in MODE 1. The COMPLETION TIME of REQUIRED ACTION A.1 is currently the most limiting/will expire before the COMPLETION TIME of REQUIRED ACTION B.1.

B.

Unit 2 was required to enter MODE 3 based on REQUIRED ACTION D.1.

When Unit 2 entered MODE 3, LCO 3.6.5 was met. None of the LCO 3.6.5 REQUIRED ACTIONS are now applicable.

C.

Unit 2 was required to enter MODE 3 based on REQUIRED ACTION D.1.

When Unit 2 entered MODE 3, simultaneous entry into CONDITIONs E and F was required. The COMPLETION TIMEs for CONDITIONs E and F have expired. Unit 2 is currently in LCO 3.6.5 CONDITION G and REQUIRED ACTION G.1.

D.

Unit 2 was required to enter MODE 3 based on REQUIRED ACTION D.1.

When Unit 2 entered MODE 3, entry into CONDITION H was required. Unit 2 was required to enter MODE 5 based on REQUIRED ACTION H.1. When Unit 2 entered MODE 5, LCO 3.6.5 became NOT APPLICABLE.

Page 89 of 100

Question:

(1 point) 90 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

1FDW-372 is discovered closed and will NOT open

1) In accordance with TS 3.7.5 (Emergency Feedwater) basis the __ (1) __ is inoperable.

2) If 1FDW-372 remains INOPERABLE, entering MODE 4 __ (2) __ required.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A.

1. 1A MDEFDWP

2. is B.

1. 1A MDEFDWP

2. is NOT C.

1. 1A EFW flow path

2. is D.

1. 1A EFW flow path

2. is NOT Page 90 of 100

Question:

(1 point) 91 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Unit 1 is in Mode 5 RB Main Purge start in progress

1) The RB Main Purge Fan will be prevented from starting if __(1)__.

2) In accordance with TS 3.6.3 Bases, all of the RB Main Purge System valves

__(2)__ be required to be operable prior to Mode 4.

Which ONE of the following completes the statements above?

A.

1. Suction pressure = 5 inches of water vacuum

2. will B.

1. 1PR-3 (RB PURGE CONTROL) indicates 5% open

2. will C.

1. Suction pressure = 5 inches of water vacuum

2. will NOT D.

1. 1PR-3 (RB PURGE CONTROL) indicates 5 % open

2. will NOT Page 91 of 100

Question:

(1 point) 92 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Initial conditions:

Unit 3 is at 25% power, starting up after a refueling outage Current conditions:

All three units experience a Station Blackout 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months later, power is still not restored Unit 3 Spent Fuel Pool (SFP) temperature is 135ºF and slowly rising AP/3/A/1700/035 (Loss of SFP Cooling and/or Level) is in progress

1) In accordance with AP/35, if the SFP begins to boil, makeup to the SFP with up to __(1)__ gpm will be required to offset the loss of inventory.

2) When power is restored, AP/35 __(2)__ restart SFP cooling pumps.

Which ONE of the following completes the statements above?

A.

1. 32

2. will B.

1. 70

2. will C.

1. 32

2. will NOT D.

1. 70

2. will NOT Page 92 of 100

Question:

(1 point) 93 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Which ONE of the following states the review and MINIMUM level of approval required by MP/0/A/1500/009, Defueling/Refueling Procedure, to place a fuel assembly into an alternate location other than the one assigned by the Core Reload Sequence per PT/0/A/0750/018?

A.

Refueling SRO must review and SM must approve B.

Reactor Engineering must review and Refueling SRO must approve C.

Reactor Engineering and Refueling SRO must review and SM must approve D.

No reviews are required by Reactor Engineering or SM, but Refueling SRO must approve Page 93 of 100

Question:

(1 point) 94 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Auxiliary Operators are being briefed to perform the alignment for U1 RCS Boration as directed by OP/1/A/1103/004A Enclosure 4.2 (RCS Boration from CBAST with 1A Bleed Transfer Pump).

In accordance with AD-OP-ALL-0203 (Reactivity Management)

1) A designated Senior Reactor Operator __(1)__ required to be physically present as oversight for non-emergency field reactivity manipulations.

2) Peer checks for non-emergency field reactivity manipulations __(2)__ be performed by Auxiliary Operators.

A.

1. is

2. may B.

1. is

2. may NOT C.

1. is NOT

2. may D.

1. is NOT

2. may NOT Page 94 of 100

Question:

(1 point) 95 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:

Reactor in MODE 6 Defueling in progress Main Bridge is located over the West Upender and has begun lowering a fuel assembly for transport to the Spent Fuel Pool in accordance with procedure Spotter sees an unidentifiable object inside the West Upender

1) In accordance with AD-OP-ONS-0001 (ONS OPERATIONS ADMINISTRATIVE COMMITMENTS), the __(1)__ can authorize withdrawing the assembly back into the mast to prevent damage to the assembly that would occur if lowered onto the object.

2) The MAXIMUM time allowed to establish Containment Closure during fuel handling is __(2)__ in accordance with SLC 16.12.6 (Fuel Damage During Fuel Handling Operations in Containment).

Which ONE of the following completes the statements above?

A.

1. Refueling SRO ONLY

2. 30 minutes B.

1. Reactor Building SRO or the Refueling SRO

2. 30 minutes C.

1. Refueling SRO ONLY

2. one hour D.

1. Reactor Building SRO or the Refueling SRO

2. one hour Page 95 of 100

Question:

(1 point) 96 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Initial conditions:

All three units are at 100% power Unit 1 entered AP/1/A/1700/032 (Loss of Letdown) at 1600 on a Saturday.

Current conditions:

It is identified that a step in the procedure cannot be performed as written It is decided that a Temporary Procedure Change will be made to AP/32 It is determined that PRA Coding could be affected by the change.

In accordance with AD-DC-ALL-0201, Development and Maintenance of Controlled Procedure Manual Procedures

1) Two members of plant Management must approve the Temporary Change, and __(1)__ of them must hold an SRO License.

2) The __(2)__ will review the change and make any needed PRA coding changes.

Which ONE of the following completes the statements above?

A.

1. one

2. SM B.

1. one

2. STA C.

1. both

2. SM D.

1. both

2. STA Page 96 of 100

Question:

(1 point) 97 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following plant conditions:

Time = 0730 (today)

Unit 1:

o GWR release of the 1A Gaseous Waste Disposal (GWD) tank at the 1/3 Station Limit is in progress Unit 3:

o Shift is preparing for a GWR release of the 3A Gaseous Waste Disposal (GWD) tank at the 1/3 Station Limit o P/A/C filter is not available for the 3A release o 3A GWD tank holdup time is 29 days Time = 1600 (today)

Unit 1:

o GWR release of 1A Gaseous Waste Disposal (GWD) tank is complete Time = 1200 (tomorrow)

Unit 3:

o P/A/C filter is available for 3A release Which ONE of the following describes the EARLIEST time that conditions are met for a non-SM qualified SRO to have the level of authority for approval of the above release in accordance with OP/3/A/1104/018 (GWD System)?

A.

0730 (today)

B.

1600 (today)

C.

0800 (tomorrow)

D.

1200 (tomorrow)

Page 97 of 100

Question:

(1 point) 98 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following U1 conditions:

MODE 3 115 gpm RCS leak from 1A2 RCP suction pipe weld 1RIA-40 (CSAE Off Gas) in alarm o O1P1599 (Est Total Pri to Sec Leakrate) = 50,400 gpd

1) The plant condition that would require the SRO to implement Emergency Dose Limits is __(1)__.

2) In accordance with the Bases of TS 3.4.13 (RCS Operational Leakage), the total RCS Pressure Boundary Leakage is __(2)__.

Which ONE of the following completes the statements above?

A.

1. 115 gpm RCS leak from 1A2 RCP suction pipe weld

2. 115 gpm + 50,400 gpd B.

1. 115 gpm RCS leak from 1A2 RCP suction pipe weld

2. 115 gpm C.

1. O1P1599 (Est Total Pri to Sec Leakrate) = 50,400 gpd

2. 115 gpm + 50,400 gpd D.

1. O1P1599 (Est Total Pri to Sec Leakrate) = 50,400 gpd

2. 115 gpm Page 98 of 100

Question:

(1 point) 99 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Reactor power = 100%

Turbine Building Flood in progress AP/1/A/1700/010, (Turbine Building Flood) initiated

1) The CRS will direct manually tripping the Reactor in accordance with __(1)__.

2) Once the Reactor is tripped, the CRS will direct feeding the Steam Generators in accordance with __(2)__.

Which ONE of the following completes the statements above?

A.

1. AP/10

2. Rule 7 B.

1. AP/10

2. Turbine Building Flood tab C.

1. the EOP

2. Rule 7 D.

1. the EOP

2. Turbine Building Flood tab Page 99 of 100

Question:

(1 point) 100 ILT21 ONS SRO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:

Initial conditions:

Time = 0900 Reactor power = 100% stable (steady state)

Subsequent conditions:

0905: A runback occurs due to a loss of a MFW Pump 0907: Plant has been stabilized at lower power level following the runback 0915: A loss of ALL CETC indication occurs 0925: An unidentified RCS leak of 15 gpm occurs 0935: Reactor trip occurs Which ONE of the following states the time when an Emergency Plan Declaration is FIRST required?

NOTE: Emergency Coordinator judgement is not to be used.

A.

0920 B.

0930 C.

0940 D.

0950 Page 100 of 100

Containment Isolation Valves 3.6.3 OCONEE UNITS 1, 2, & 3 3.6.3-1 Amendment Nos. 300, 300, & 300 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS

NOTES------------------------------------------------------

1.

Penetration flow paths except for 48 inch purge valve penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for system(s) made inoperable by containment isolation valves.

CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE------------

Only applicable to penetration flow paths with two containment isolation valves.

One or more penetration flow paths with one containment isolation valve inoperable.

A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-automatic power operated valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

AND 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

Containment Isolation Valves 3.6.3 ACTIONS OCONEE UNITS 1, 2, & 3 3.6.3-2 Amendment Nos. 300, 300, & 300 CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2

NOTE-----------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B.

NOTE------------

Only applicable to penetration flow paths with two containment isolation valves.

One or more penetration flow paths with two containment isolation valves inoperable.

B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-automatic power operated valve, closed manual valve, or blind flange.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued)

Containment Isolation Valves 3.6.3 ACTIONS (continued)

OCONEE UNITS 1, 2, & 3 3.6.3-3 Amendment Nos. 300, 300, & 300 CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE-----------

Only applicable to penetration flow paths with only one containment isolation valve and a closed system.

One or more penetration flow paths with one containment isolation valve inoperable.

C.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-automatic power operated valve, closed manual valve, or blind flange.

AND C.2

NOTE------------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Once per 31 days D.

Required Action and associated Completion Time not met.

D.1 Be in MODE 3.

AND D.2 Be in MODE 5.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours

Reactor Building Spray and Cooling Systems 3.6.5 OCONEE UNITS 1, 2, & 3 3.6.5-1 Amendment Nos. 300, 340, & 300 3.6 CONTAINMENT SYSTEMS 3.6.5 Reactor Building Spray and Cooling Systems LCO 3.6.5 Two reactor building spray trains and three reactor building cooling trains shall be OPERABLE.

NOTE----------------------------------------------

Only one train of reactor building spray and two trains of reactor building cooling are required to be OPERABLE during MODES 3 and 4.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS

NOTE--------------------------------------------------------

LCO 3.0.4 is not applicable for Unit 2.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One reactor building spray train inoperable in MODE 1 or 2.

A.1 Restore reactor building spray train to OPERABLE status.

7 days AND 14 days from discovery of failure to meet the LCO B.

One reactor building cooling train inoperable in MODE 1 or 2.

B.1 Restore reactor building cooling train to OPERABLE status.

7 days AND 14 days from discovery of failure to meet the LCO (continued)

Reactor Building Spray and Cooling Systems 3.6.5 ACTIONS (continued)

OCONEE UNITS 1, 2, & 3 3.6.5-2 Amendment Nos. 300, 300, & 300 CONDITION REQUIRED ACTION COMPLETION TIME C.

One reactor building spray train and one reactor building cooling train inoperable in MODE 1 or 2.

C.1 Restore one train to OPERABLE status.

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

Required Action and associated Completion Time of Condition A, B, or C are not met.

D.1 Be in MODE 3.

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

One required reactor building cooling train inoperable in MODE 3 or 4.

E.1 Restore required reactor building cooling train to OPERABLE status.

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

One required reactor building spray train inoperable in MODE 3 or 4.

F.1 Restore required reactor building spray train to OPERABLE status.

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

Required Action and associated Completion Time of Condition E or F not met.

G.1 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Reactor Building Spray and Cooling Systems 3.6.5 ACTIONS (continued)

OCONEE UNITS 1, 2, & 3 3.6.5-3 Amendment Nos. 300, 300, & 300 CONDITION REQUIRED ACTION COMPLETION TIME H.

Two reactor building spray trains inoperable in MODE 1 or 2.

OR Two reactor building cooling trains inoperable in MODE 1 or 2.

OR Any combination of three or more trains inoperable in MODE 1 or 2.

OR Any combination of two or more required trains inoperable in MODE 3 or 4.

H.1 Enter LCO 3.0.3.

Immediately

EFW System 3.7.5 OCONEE UNITS 1, 2, & 3 3.7.5-1 Amendment Nos. 417, 419, & 418 3.7 PLANT SYSTEMS 3.7.5 Emergency Feedwater (EFW) System LCO 3.7.5 The EFW System shall be OPERABLE as follows:

a.

Three EFW pumps shall be OPERABLE, and

b.

Two EFW flow paths shall be OPERABLE.

NOTE------------------------------------------

Only one motor driven emergency feedwater (MDEFW) pump and one EFW flow path are required to be OPERABLE in MODE 4.

APPLICABILITY:

MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

NOTE----------------------------------------------------

LCO 3.0.4.b is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One MDEFW pump inoperable in MODE 1, 2, or 3.

A.1 Restore MDEFW pump to OPERABLE status.

7 days AND 10 days from discovery of failure to meet the LCO B.

Turbine driven EFW pump inoperable in MODE 1, 2, or 3.

OR One EFW flow path inoperable in MODE 1, 2, or 3.

B.1 Restore turbine driven EFW pump and EFW flow path to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 10 days from discovery of failure to meet the LCO (continued)

EFW System 3.7.5 ACTIONS (continued)

OCONEE UNITS 1, 2, & 3 3.7.5-2 Amendment Nos. 300, 300, & 300 CONDITION REQUIRED ACTION COMPLETION TIME C.

Two MDEFW pumps inoperable in MODE 1, 2, or 3.

C.1 Restore one MDEFW pump to OPERABLE status.

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

Required Action and associated Completion Time of Condition A, B, or C not met.

OR Turbine driven EFW pump and one EFW flow path inoperable in MODE 1, 2, or 3.

D.1 Be in MODE 3.

AND D.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 24 hours (continued)

EFW System 3.7.5 ACTIONS (continued)

OCONEE UNITS 1, 2, & 3 3.7.5-3 Amendment Nos. 300, 300, & 300 CONDITION REQUIRED ACTION COMPLETION TIME E.

Three EFW pumps inoperable in MODE 1, 2, or 3.

OR Two EFW flow path inoperable in MODE 1, 2, or 3.

E.1

NOTE------------

LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one EFW pump and one EFW flow path are restored to OPERABLE status.

Initiate action to restore one EFW pump and one EFW flow path to OPERABLE status.

Immediately F.

Required MDEFW pump inoperable in MODE 4.

OR Required EFW flow path inoperable in MODE 4.

F.1 Initiate action to restore required MDEFW pump and required EFW flow path to OPERABLE status.

Immediately

Examination KEY ILT21 ONS SRO NRC Examination Q A Q A Q A Q A 1

D 26 B

51 A

76 C

2 D

27 D

52 C

77 A

3 B

28 D

53 A

78 B

4 A

29 D

54 D

79 C

5 C

30 B

55 B

80 C

6 A

31 A

56 D

81 B

7 D

32 D

57 A

82 D

8 D

33 B

58 C

83 D

9 D

34 C

59 C

84 D

10 D

35 A

60 A

85 C

11 B

36 B

61 D

86 D

12 A

37 B

62 C

87 B

13 D

38 B

63 C

88 B

14 C

39 C

64 B

89 B

15 B

40 A

65 A

90 A

16 D

41 D

66 C

91 D

17 C

42 D

67 B

92 B

18 A

43 A

68 D

93 B

19 D

44 C

69 A

94 C

20 D

45 B

70 D

95 B

21 B

46 D

71 B

96 B

22 D

47 A

72 B

97 D

23 B

48 A

73 D

98 D

24 B

49 A

74 D

99 B

25 B

50 A

75 A

100 B

Printed 6/10/2021 12:08:44 PM Page 1 of 1

ML21174A045

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