ML19032A142

Final RO Written Exam 2019-301 - Delay Release Two Years

ML19032A142
Person / Time
Site:	Brunswick
Issue date:	01/22/2019
From:	Division of Reactor Safety II
To:
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Download: ML19032A142 (78)

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ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: //201

Facility / Unit: Brunswick Unit 1/2 Region:

I II III IV Reactor Type: W CE BW GE Start Time:

Finish Time:

Instructions Use the answer sheets Srovided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results Examination Value

________ Points Applicant's Score

________ Points Applicant's Grade

________ Percent

RO Written Exam Reference Index

1. 0EOP-01-UG, Users Guide, Attachments:

5 (Drywell Spray Initiation Limit) 8 (Core Spray NPSH Limit) 13 (Core Spray Vortex Limit) 25 (Unit 1 RPV Level at LL4) 27 (Unit 1 RPV Level at LL5)

2. 0EOP-03-SCCP, Table SC-3, Area Radiation Limits

3. LL-30024 SH0006, 125/250 Volt DC System Control Building Distribution Panel 3A

1. Unit Two is performing a shutdown IAW 0GP-05, Unit Shutdown.

Which one of the following completes both statements below?

An insert rod block will first be enforced when reactor power lowers below (1).

Use of the Emergency Rod In switch (2) bypass the enforcement of the insert rod block.

(1) 27.8%

(2) will (1) 27.8%

(2) will NOT (1) 19.1%

(2) will (1) 19.1%

(2) will NOT A.

B.

C.

D.

Page: 1

2. Which one of the following completes the statement below?

To maintain adequate net positive suction head (NPSH), the Unit Two recirc pumps will runback to (1) when (2) flow is <16.4% of rated.

(1) Limiter #1 (2) total feedwater (1) Limiter #1 (2) individual feed pump suction (1) Limiter #2 (2) total feedwater (1) Limiter #2 (2) individual feed pump suction A.

B.

C.

D.

Page: 2

3. With Unit One at 100% power, 125 VDC Switchboard 3A Circuit 3 trips open.

Subsequently, the following conditions exist:

Drywell pressure is 2 psig Reactor water level is 90 inches and lowering Reactor pressure is 400 psig and lowering

[Reference Provided]

Which one of the following completes both statements below?

RHR Loop A pumps (1) running.

E11-F015A, Inboard Injection Valve, (2) automatically open.

(1) are (2) will (1) are (2) will NOT (1) are NOT (2) will (1) are NOT (2) will NOT A.

B.

C.

D.

Page: 3

4. Unit Two is in MODE 3 following a scram from 100% power.

RWCU is lined up for rejecting to the condenser hotwell.

Which one of the following completes both statements below?

IAW the hardcard, Post Scram Level Control - High RPV Level, maintain pump flow less than or equal to 290 gpm and (1) less than 130°F by throttling G31-F033, RWCU Reject Flow Control Vlv.

If 135°F is exceeded, the G31-F004, RWCU Outboard Isol Vlv, (2) auto close.

(1) Regen HX Outlet temperature (2) will (1) Regen HX Outlet temperature (2) will NOT (1) Filter Inlet temperature (2) will (1) Filter Inlet temperature (2) will NOT A.

B.

C.

D.

Page: 4

5. RHR Loop B is operating in Shutdown Cooling (SDC) on Unit Two with the following parameters:

Reactor pressure 10 psig Reactor mode switch Shutdown MSIVs Closed 2B RHRSW Pump Operating 2B RHR Pump Operating 2A NSW Pump Operating 2B NSW Pump Under clearance Conventional Service Water Pumps are aligned to CSW Header Subsequently, A-02 (2-9) RHR SW Pmp II - Suct Hdr Press Low, is received due to a trip of the 2A NSW pump.

Which one of the following completes both statements below?

The 2B RHRSW pump will trip __(1)__.

With no operator action, a mode change __(2)__ occur.

(1) immediately (2) will (1) immediately (2) will NOT (1) after 10 seconds (2) will (1) after 10 seconds (2) will NOT A.

B.

C.

D.

Page: 5

6. Following a scram on Unit Two, HPCI is operating in pressure control IAW the hardcard, HPCI Pressure Control in EOPs.

0EOP-01-SEP-10, Circuit Alteration Procedure, has NOT been implemented.

Subsequently, A-01 (1-5) Suppression Chamber Lvl Hi-Hi, (red bar) alarms.

Which one of the following completes both statements below?

The E41-F041 and E41-F042, Torus Suction Valves, (1) automatically open.

The E41-F008, Bypass to CST Valve, (2) automatically close.

(1) will (2) will (1) will (2) will NOT (1) will NOT (2) will (1) will NOT (2) will NOT A.

B.

C.

D.

Page: 6

7. Unit One is at 100% power when a LOCA occurs.

Current indications are as follows:

Reactor pressure 350 psig Reactor level 110 inches Drywell pressure 2.2 psig Which one of the following completes both statements below?

E21-F005A, Core Spray A Inboard Injection Valve, (1) open.

Core Spray Loop A flow, as indicated on the P601 panel indicator E21-FI-R601A, Pump 1A Discharge Flow, is (2).

(1) is (2) 0 gpm (1) is (2) 500 gpm (1) is NOT (2) 0 gpm (1) is NOT (2) 500 gpm A.

B.

C.

D.

Page: 7

8. Unit Two is performing an emergency depressurization during an ATWS.

IAW ATWS Procedure, which one of the following identifies when Core Spray can be used for injection?

When level is below 90 inches.

When TAF cannot be maintained.

When LL3 cannot be maintained.

When LL4 cannot be maintained.

A.

B.

C.

D.

Page: 8

9. Unit One is at 100% power with DG1 under clearance.

Subsequently, a LOOP with an ATWS occurs.

The C41-CS-S1 (SLC Pump A & B) switch is placed in the Pump A/B run position.

Initial SLC tank level is approximately 2400 gallons.

Which one of the following completes both statements below?

SLC Explosive Squib Valve, C41-F004A, (1) fire.

IAW 1OP-05, Standby Liquid Control System Operating Procedure, Section 6.1.2, Manual Initiation of SLC, it will take approximately (2) to completely empty the SLC Storage Tank.

(1) will (2) 29 minutes (1) will (2) 58 minutes (1) will NOT (2) 29 minutes (1) will NOT (2) 58 minutes A.

B.

C.

D.

Page: 9

10. Unit One is at 30% rated thermal power when A-05 (6-7), Turb CV Fast Clos/SV Trip Bypass, alarms due to the failure of both RPS Channel A pressure switches.

Which one of the following completes both statements below?

If a load reject were to occur (actuation of the power/load unbalance circuit), a half scram (1) occur.

IAW APP A-05 (6-7), reactor power is required to be reduced to less than (2) rated thermal power within two hours.

(1) will (2) 20.6%

(1) will (2) 26%

(1) will NOT (2) 20.6%

(1) will NOT (2) 26%

A.

B.

C.

D.

Page: 10

11. Which one of the following completes the statement below?

The RBM Channel A will automatically bypass itself when its primary reference is below the RBM low power setpoint.

APRM 1 APRM 2 APRM 3 APRM 4 A.

B.

C.

D.

Page: 11

12. A Unit One reactor shutdown is in progress.

All IRMs on range 3 reading between 15 and 20.

IRM B detector is failing downscale.

Which one of the following completes both statements below?

IAW APP A-05 (1-4) IRM Downscale, the alarm setpoint is (1) +/-1.5on the 125 scale.

When the IRM downscale alarm is received, a rod block (2) be generated.

(1) 3 (2) will (1) 3 (2) will NOT (1) 5 (2) will (1) 5 (2) will NOT A.

B.

C.

D.

Page: 12

13. Which one of the following completes the statement below concerning the IRM System?

The (1) passes only one of two sets of frequencies depending on the IRM range selector switch between ranges (2).

(1) Pulse Preamplifier (2) 5 to 6 (1) Pulse Preamplifier (2) 6 to 7 (1) Voltage Preamplifier (2) 5 to 6 (1) Voltage Preamplifier (2) 6 to 7 A.

B.

C.

D.

Page: 13

14. Unit Two is in MODE 5 with the RPS shorting links removed.

Which one of the following identifies the condition that will cause an actuation of RPS?

SRM C fails upscale SRM Channel C period meter fails upscale SRM C drawer switch S1 placed in standby Loss of SRM C High voltage power supply A.

B.

C.

D.

Page: 14

15. A plant startup is in progress on Unit Two. A control rod block occurs with the following nuclear instrument indications:

SRM Counts Position IRM Counts Range A

95 Mid Position A

25/125 3

B 190 Mid Position B

60/125 2

C 6x104 Full In C

35/125 3

D 155 Mid Position D

15/125 3

E 65/125 2

F 55/125 3

G 30/125 3

H 25/125 3

Which one of the following completes the statement below?

This rod block can be cleared by (1) or it can be bypassed by ranging (2) to range 3.

(1) inserting SRM A (2) IRM B (1) inserting SRM A (2) IRM E (1) withdrawing SRM C (2) IRM B (1) withdrawing SRM C (2) IRM E A.

B.

C.

D.

Page: 15

16. A startup is being performed on Unit Two with power currently at 20%.

APRMs 1 and 2 have the following number of operable LPRM inputs:

Level A

B C

D APRM 1 4

3 5

4 APRM 2 5

4 2

6 Which one of the following completes both statements below?

APRM 1 (1) generate a rod block signal.

APRM 2 (2) generate a rod block signal.

(1) will (2) will (1) will (2) will NOT (1) will NOT (2) will (1) will NOT (2) will NOT A.

B.

C.

D.

Page: 16

17. Which one of the following completes the statement below?

The RCIC minimum flow line discharges to:

HPCI RHR Loop A RHR Loop B Core Spray Loop B A.

B.

C.

D.

Page: 17

18. Unit One was operating at 100% power with Core Spray Pump 1B under clearance when a small break LOCA occurs. The ADS switches have been aligned as shown.

Annunciator A-03 (3-2) Auto Depress Relays Energized (red bar) is illuminated.

Based on the plant indications above, which one of the following identifies the ADS response if reactor water level remains less than LL-3 for 2 minutes?

ADS will not auto initiate.

ADS will auto initiate if 1A Core Spray Pump is running.

ADS will auto initiate if both RHR A Pump and RHR C Pump are running.

ADS will auto initiate if both RHR B Pump and RHR D Pump are running.

A.

B.

C.

D.

Page: 18

19.

Unit Two is at 100% power when A-01 (3-7), Suppression Chamber Lvl Hi/Lo (blue bar), illuminates.

CAC-LI-4177, Supp Pool Level, indicator on the left, indicates as shown.

Which one of the following completes both statements below?

The alarm and indications are consistent with a (1) suppression pool level.

Entry into PCCP (2) required.

(1) low (2) is (1) low (2) is NOT (1) high (2) is (1) high (2) is NOT A.

B.

C.

D.

Page: 19

20. Which one of the following completes both statements below concerning the Unit Two Group I isolation signal for Main Steam Line Flow High not in RUN.

This isolation signal is required on Unit Two because its bypass valve capacity results in inadequate margin to the (1).

High steam line flow sensed in at least (2) steam lines will auto close all MSIVs.

(1) LHGR limit (2) two (1) LHGR limit (2) three (1) MCPR (2) two (1) MCPR (2) three A.

B.

C.

D.

Page: 20

21. Unit Two is operating at 100% power.

Which one of the following completes the statement below?

2B RHR Pump is powered from Bus (1) which is powered from BOP Bus (2).

(1) E2 (2) 1C (1) E2 (2) 1D (1) E4 (2) 2C (1) E4 (2) 2D A.

B.

C.

D.

Page: 21

22. A Unit One core shuffle is in progress with the mode switch in REFUEL.

All control rods are fully inserted.

The refueling bridge is located in the Spent Fuel Pool.

The hoist is at the normal up position.

The Refuel SRO gives the following directions:

1) Move the bridge to core location 31-18.

2) Lower the main hoist to fuel bundle 31-18.

3) Close the grapple to latch fuel bundle 31-18.

4) Raise fuel bundle 31-18 to the normal up position.

Which one of the following identifies when the A-05 (2-2) Rod Out Block (yellow bar),

will first illuminate during the performance of the steps above?

Step 1.

Step 2.

Step 3.

Step 4.

A.

B.

C.

D.

Page: 22

23. Unit One is at 100% power when a Group I isolation occurs.

Reactor pressure peaks at 1145 psig during the transient.

Which one of the following completes the statement below?

SRV amber lights on the RTGB will illuminate.

Four Seven Eight Eleven A.

B.

C.

D.

Page: 23

24. Given the following conditions:

Reactor pressure 1130 psig Torus pressure 5.3 psig

[Reference Provided]

Which one of the following completes both statements below?

The expected ERFIS tail pipe temperature for an open SRV is (1).

The device that triggers annunciation of A-03 (1-10) Safety / Relief Valve Open (red bar) is the (2).

(1) ~227°F (2) sonic detector (1) ~227°F (2) temperature recorder (1) ~320°F (2) sonic detector (1) ~320°F (2) temperature recorder A.

B.

C.

D.

Page: 24

25. Unit Two was at 100% power when a reactor scram occurred and the main turbine/generator was manually tripped due to a reactor scram.

Which one of the following completes both statements below?

The Motor Suction Pump will auto start when the main shaft oil pump suction pressure first lowers to (1).

IAW 2OP-26, Turbine System Operating Procedure, Section 6.2.2, Shutdown After Unplanned Trip, the TBCCW To Main Turb Oil Cooler temperature controller setpoint is required to be adjusted to maintain bearing inlet oil temperature at (2).

(1) 10 psig (2) 90°F (1) 10 psig (2) 110°F (1) 15 psig (2) 90°F (1) 15 psig (2) 110°F A.

B.

C.

D.

Page: 25

26. Unit Two startup is in progress with reactor power at 30%.

RFP B is in service with the FW-FV-47, RFP B Recirc Vlv, open with its control switch in the AUTO position.

Which one of the following completes both statements below?

The FW-FV-47, RFP B Recirc Vlv, will auto close when feedwater flow first increases above (1).

If UA-03 (4-1), RFP B Turbine Tripped (red bar), alarms, the FW-FV-47, RFP B Recirc Vlv, indication will be (2).

(1) 2.45 Mlbm/hr (2) red (1) 2.45 Mlbm/hr (2) green (1) 6.25 Mlbm/hr (2) red (1) 6.25 Mlbm/hr (2) green A.

B.

C.

D.

Page: 26

27. Which one of the following completes the statement below?

The Unit Two HPCI system initiation logic is powered from 125 VDC panel:

1A 2A 3A 4A A.

B.

C.

D.

Page: 27

28. Unit One is operating at 80% power.

A reactor water level control malfunction has caused the recirc pumps to runback to Limiter 1.

Which one of the following identifies the current speed of the Recirc Pumps?

48%

45%

34%

20%

A.

B.

C.

D.

Page: 28

29. Primary containment venting of the torus on Unit One is being performed IAW 1OP-10, Standby Gas Treatment System Operating Procedure, Section 6.3.2, Venting Containment Via SBGT, with primary containment pressure lowering.

Subsequently, UA-03 (4-5), Process Rx Bldg Vent Rad Hi (blue bar), is received.

Which one of the following completes both statements below?

The Standby Gas Train Fans "Fan On" light (1) be illuminated.

Primary containment pressure (2) continue to lower.

(1) will (2) will (1) will (2) will NOT (1) will NOT (2) will (1) will NOT (2) will NOT A.

B.

C.

D.

Page: 29

30. Which one of the following identifies the normal source of power to Caswell Beach Bus A?

Common A Southport Feeder Town Creek 230 kV Feeder Unit One 230 kV Transformer Bus A.

B.

C.

D.

Page: 30

31. Which one of the following completes both statements below?

The Stack Radiation Monitor is capable of being provided with power from either unit via a(an) (1) transfer device.

If the Stack Rad Monitor Power Transfer Device has/was transferred to alternate, (2) is supplying power to the Stack Radiation Monitor.

(1) automatic (2) Unit One (1) automatic (2) Unit Two (1) manual (2) Unit One (1) manual (2) Unit Two A.

B.

C.

D.

Page: 31

32. Unit Two has lost the 2B-2 battery and the 2B-2 battery charger.

Which one of the following completes both statements below?

Division II 250 VDC loads (1) operate.

Unit Two Battery Bus (2) is de-energized.

(1) will still (2) N/P (1) will still (2) N (1) will NOT (2) N/P (1) will NOT (2) N A.

B.

C.

D.

Page: 32

33. DG2 was running in Control Room Manual during performance of the 24-month load test portion of 0PT-12.2B, No. 2 Diesel Generator Monthly Load Test, when it tripped due to high lube oil temperature.

Which one of the following completes both statements below concerning the operation of DG2?

The high lube oil temperature trip setpoint is (1).

If a LOOP occurs, with the high lube oil temperature condition still present, DG2 (2) auto start.

(1) 180°F (2) will (1) 180°F (2) will NOT (1) 190°F (2) will (1) 190°F (2) will NOT A.

B.

C.

D.

Page: 33

34. Unit Two is operating at 100% power when Process Reactor Building Ventilation Radiation Monitor A (D12-RM-K609A) fails upscale.

NOTE: Valve Nomenclature 2A-BFIV-RB, RB Vent Inbd Supply Isol Valve 2B-BFIV-RB, RB Vent Otbd Supply Isol Valve 2C-BFIV-RB, RB Vent Inbd Exhaust Isol Valve 2D-BFIV-RB, RB Vent Otbd Exhaust Isol Valve Which one of the following completes both statements below?

Reactor building ventilation (1) isolation valves will isolate.

Standby Gas Treatment train(s) (2) will auto start.

(1) inboard ONLY (2) A ONLY (1) inboard ONLY (2) A & B (1) inboard & outboard (2) A ONLY (1) inboard & outboard (2) A & B A.

B.

C.

D.

Page: 34

35. Which one of the following completes the statement below?

The alternate power supply to the Electric Fire Pump is Bus:

E1 E2 E3 E4 A.

B.

C.

D.

Page: 35

36. Unit Two is at 100% and no cooling water is available to the vital header.

Temperatures are rising in the reactor building and area temperatures in the RHR and Core Spray rooms are at 102°F Which one of the following completes both statements below concerning the status of RHR and Core Spray room coolers?

RHR room coolers (1) running.

Core Spray room coolers (2) running.

(1) are (2) are (1) are (2) are NOT (1) are NOT (2) are (1) are NOT (2) are NOT A.

B.

C.

D.

Page: 36

37. Unit Two is operating at 100% power when a jet pump failure occurs.

IAW 2AOP-4.0, Low Core Flow, which one of the following completes the statement below?

Total core flow from Process Computer Point (1) will be inaccurate because it will indicate (2) than actual core flow.

(1) U2CPWTCF (2) higher (1) U2CPWTCF (2) lower (1) U2NSSWDP (2) higher (1) U2NSSWDP (2) lower A.

B.

C.

D.

Page: 37

38. A complete loss of off site power occurs with a loss of all DGs.

IAW 1(2)EOP-01-SBO, Station Blackout, which one of the following completes both statements below?

The battery chargers are required to be in operation within (1).

IF either division battery charger cannot be restored, THEN load strip the affected battery within (2).

(1) 30 minutes (2) 60 minutes (1) 30 minutes (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (1) 60 minutes (2) 60 minutes (1) 60 minutes (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> A.

B.

C.

D.

Page: 38

39. The following battery chargers have no power: 2A-1, 2A-2, 2B-1, and 2B-2.

Battery Charger 2A-1 DC Output Breaker is tripped open.

Which one of the following completes both statements below?

The Bus 2A-1 DC voltage meter, 2-BAT-VM-737 on Panel XU-1, will indicate (1).

IAW 0AOP-39.0, Loss of DC Power, loads must be removed to maintain battery voltage greater than or equal to a minimum of (2).

(1) 0 VDC (2) 105 VDC (1) 0 VDC (2) 129 VDC (1) Bus 2A-1 DC voltage (2) 105 VDC (1) Bus 2A-1 DC voltage (2) 129 VDC A.

B.

C.

D.

Page: 39

40. Unit One is performing a unit shutdown for a refueling outage.

A rapid shutdown is NOT desired.

IAW 1OP-26, Turbine System Operating Procedure, Section 6.2.1, Normal Shutdown, which one of the following completes both statements below?

Prior to tripping the main turbine, power must be reduced to (1).

IF the bypass valves do NOT open when the Emergency Trip System trip pushbutton is depressed, THEN the initial plant response is a(n) (2) in core power.

(1) 23 - 26%

(2) decrease (1) 23 - 26%

(2) increase (1) 100 - 110 MWe (2) decrease (1) 100 - 110 MWe (2) increase A.

B.

C.

D.

Page: 40

41. Which one of the following completes both statements below?

IAW RSP, the reactor is shutdown without boron under all conditions if (1) rod(s) is(are) fully withdrawn.

If TS LCO 3.1.1, Shutdown Margin, is not met in MODE 3 following a scram, the required action is to fully insert all insertable control rods (2).

(1) ONLY one (2) immediately (1) ONLY one (2) within one hour (1) NO more than 10 (2) immediately (1) NO more than 10 (2) within one hour A.

B.

C.

D.

Page: 41

42. Unit One has been operating at 100% power for the last 12 months.

RVCP is being implemented following a LOOP.

Which one of the following completes both statements below?

IAW RVCP, Step RC/P-3, IF any SRV is cycling, THEN open SRVs until pressure drops to (1).

The RCIC System has a capacity approximately equal to the reactor water boil-off rate (2) minutes after shutdown.

(1) 950 psig (2) 20 (1) 950 psig (2) 60 (1) 1050 psig (2) 20 (1) 1050 psig (2) 60 A.

B.

C.

D.

Page: 42

43. Unit Two is performing a RWCU blowdown to radwaste IAW Post Scram Level Control

- High RPV Level Hardcard.

The following indications are observed:

Which one of the following identifies the RWCU reject flowrate?

8 gpm 72 gpm 80 gpm 176 gpm A.

B.

C.

D.

Page: 43

44. Following a line break in the drywell, Unit One conditions are:

Drywell pressure 8 psig Drywell temperature 220°F Torus pressure 7 psig Torus level

-28 inches

[Reference Provided]

Which one of the following completes the statement below IAW PCCP?

Initiation of (1) Spray is required, which must be terminated at (2).

(1) Torus (2) 1.7 psig (1) Torus (2) 2.5 psig (1) Drywell (2) 1.7 psig (1) Drywell (2) 2.5 psig A.

B.

C.

D.

Page: 44

45. Unit Two is operating at 100% power when a loss of feedwater heating transient occurs.

Which one of the following completes the statement below IAW Unit Two Tech Specs?

The MCPR safety limit for this condition is (1).

IAW 2AOP-03.0, Positive Reactivity Addition, IF the current operating point is outside the analyzed region of the Power/Flow Map, THEN action must be taken to restore operation to within the analyzed region within (2).

(1) 1.07 (2) 15 minutes (1) 1.07 (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (1) 1.09 (2) 15 minutes (1) 1.09 (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> A.

B.

C.

D.

Page: 45

46. 0AOP-32.0, Plant Shutdown From Outside Control Room, is being performed.

SRV B was the last SRV to be closed while performing a cooldown, no SRVs are currently open.

Which one of the following completes both statements below?

SRV (1) is the next SRV to be opened IAW the sequence established in 0AOP-32.0.

IAW 0AOP-32.0 the cooldown rate (2) allowed to exceed 100°F/Hr.

(1) E (2) is (1) E (2) is NOT (1) G (2) is (1) G (2) is NOT A.

B.

C.

D.

Page: 46

47. Unit Two is operating at 100% power.

UA-01 (1-9) Conv Hdr Serv Water Press-Low (yellow bar) alarms.

SW to TBCCW Hxs Outbd and Inbd Isolation valves, SW-V3 and SW-V4, have automatically throttled.

Conventional Service water header pressure is 35 psig, due to a leak.

IAW 0AOP-19.0, Conventional Service Water System Failure, which one of the following completes both statements below?

The standby CSW pump selected to the CSW header, auto-started at (1).

A reactor scram (2) required.

(1) 40 psig (2) is (1) 40 psig (2) is NOT (1) 42 psig (2) is (1) 42 psig (2) is NOT A.

B.

C.

D.

Page: 47

48. Unit Two is at 15% power with the following conditions:

Division I PNS header pressure 90 psig Division II PNS header pressure 93 psig Div I Backup N2 supply pressure 98 psig Div II Backup N2 supply pressure 90 psig Which one of the following completes both statements below?

The Backup Nitrogen System (1) designed to supply pneumatics to the Suppression Chamber to Drywell Vacuum Breakers (A-J).

A reactor scram (2) required IAW 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures.

(1) is (2) is (1) is (2) is NOT (1) is NOT (2) is (1) is NOT (2) is NOT A.

B.

C.

D.

Page: 48

49. Following a manual reactor scram on Unit Two from 35% power, the OATC places the MODE switch to the STARTUP/HOT STANDBY position with the following Main Steam Line Flow indications:

Which one of the following completes both statements below?

The B32-F019 and F020, Reactor Recirc Sample Inboard and Outboard Isolation Valves, (1) auto close.

IAW 0OI-37.3, Reactor Scram Procedure Basis Document, RVCP (2) required to be entered.

(1) will (2) is (1) will (2) is NOT (1) will NOT (2) is (1) will NOT (2) is NOT A.

B.

C.

D.

Page: 49

50. Unit Two is in Cold Shutdown with both Reactor Recirculation pumps shutdown.

SDC has been lost. The crew has determined that Alternate SDC using the SRVs is required.

Which one of the following completes the statement below for establishing alternate shutdown cooling with the SRVs IAW 0AOP-15.0, Loss of Shutdown Cooling?

RPV Level must be raised and maintained (1), which can be verified on the (2) Level instrument.

(1) 200 to 220 inches (2) N026, Wide Range (1) 200 to 220 inches (2) N027, Shutdown Range (1) greater than 254 inches (2) N026, Wide Range (1) greater than 254 inches (2) N027, Shutdown Range A.

B.

C.

D.

Page: 50

51. Unit Two is in a refueling outage performing the first fuel shuffle.

A fuel bundle is inadvertently dropped in the "cattle chute".

UA-03 (4-7) Area Rad New Fuel Storage High alarms.

The following indications are observed for ARM Channel 2-28, U-2 RX Bldg Between RX and Fuel Storage Pool Elev 117 Ft:

[Reference Provided]

Which one of the following completes both statements below for this condition?

SCCP (1) required to be entered.

0AOP-5.0, Radioactive Spills, High Radiation, and Airborne Activity, states that Control Room Emergency Ventilation is required to be in service within (2).

(1) is (2) 15 minutes (1) is (2) 20 minutes (1) is NOT (2) 15 minutes (1) is NOT (2) 20 minutes A.

B.

C.

D.

Page: 51

52. Unit Two was operating at 100% power with torus cooling in service for HPCI testing.

Subsequently, a LOCA occurs, with the following plant conditions:

Drywell pressure 1.2 psig and rising RPV water level 65 inches and stable RPV pressure 400 psig and slowly lowering Torus Temperature 125°F and rising Which one of the following completes both statements below?

As drywell pressure rises, the E11-F024A, Torus Cooling Isolation Valve, will first auto close at (1).

IAW PCCP T/T leg, Containment Cooling (Table M-3, Minimum Containment Cooling Requirements) is required to be established before torus water temperature reaches (2).

(1) 1.7 psig (2) 150°F (1) 1.7 psig (2) 190°F (1) 2.7 psig (2) 150°F (1) 2.7 psig (2) 190°F A.

B.

C.

D.

Page: 52

53. Unit Two is executing RVCP following a Group I isolation from 100% power. HPCI is being operated in pressure control (per hardcard).

IAW 2OP-19, High Pressure Coolant Injection System Operating Procedure, which one of the following completes both statements below?

In order to lower reactor pressure, the E41-F008, Bypass To CST Vlv, is required to be throttled in the (1) direction.

IF E41-F008 is throttled too far in this direction, THEN HPCI (2).

(1) open (2) speed may be reduced below 2100 RPM (1) open (2) steam flow may exceed the ability of RCIC to maintain reactor vessel level (1) closed (2) speed may be reduced below 2100 RPM (1) closed (2) steam flow may exceed the ability of RCIC to maintain reactor vessel level A.

B.

C.

D.

Page: 53

54. Unit One is operating at 100% power and the crew has entered 0AOP-14.0, Abnormal Primary Containment Conditions, due to a leaking SRV.

Which one of the following completes both statements below?

Primary Containment Control Procedure (PCCP) is required to be entered when the torus water temperature first exceeds (1).

When PCCP is entered, 0AOP-14.0 is required to be (2).

(1) 95°F (2) performed concurrently (1) 95°F (2) exited (1) 105°F (2) performed concurrently (1) 105°F (2) exited A.

B.

C.

D.

Page: 54

55. Unit One is spraying the drywell IAW 0EOP-01-SEP-02, Drywell Spray Procedure, with the following containment parameters:

Drywell temperature 335°F and lowering (peaked at 340°F)

Drywell pressure 5 psig and lowering (peaked at 12 psig)

[Reference Provided]

Which one of the following completes the statement below IAW SEP-02 and PCCP?

Drywell sprays:

may continue until torus level reaches -21 inches may continue until drywell pressure reaches 2.5 psig are required to be immediately stopped because the Drywell Spray Initiation Limit has been violated are required to be immediately stopped because Emergency Depressurization is required A.

B.

C.

D.

Page: 55

56. Following a LOCA on Unit Two, the 2A and 2B Core Spray pumps are injecting from their normal suction source, and plant conditions are as follows:

Reactor water level 55 inches and rising Reactor pressure 150 psig Torus temperature 220°F Torus pressure 10.5 psig Torus level

-43 inches CST level 11 feet 2A Core Spray pump flow 5000 gpm 2B Core Spray pump flow 2800 gpm

[Reference Provided]

Which one of the following completes both statements below?

Core Spray pump(s) (1) damage is expected due to (2).

(1) 2A ONLY (2) air entrainment (1) 2A ONLY (2) pump cavitation (1) 2A and 2B (2) air entrainment (1) 2A and 2B (2) pump cavitation A.

B.

C.

D.

Page: 56

57. During an accident, Unit Two plant conditions are:

Reactor water level

-35 inches, lowering RPV pressure 50 psig Injection sources Core Spray A injection at 5000 gpm Core Spray B injection at 5000 gpm Which one of the following completes the statement below IAW the definition of "Adequate Core Cooling" in 0OI-37.4, Reactor Vessel Control Procedure Basis Document?

For the above conditions, (1) Core Spray pump(s) is/are required, as long as level remains above (2).

(1) ONLY one (2) LL-5 (1) ONLY one (2) the elevation of the jet pump suctions (1) both of the (2) LL-5 (1) both of the (2) the elevation of the jet pump suctions A.

B.

C.

D.

Page: 57

58. Unit Two is operating at 100% power when the following alarm is received:

UA-05 (6-7), Rx Bldg Static Press Diff - Low (blue bar)

Reactor building pressure has stabilized at a negative value.

Which one of the following completes both statements below?

Reactor Building Supply and Exhaust Fans (1) tripped.

SCCP (2) required to be entered.

(1) have (2) is (1) have (2) is NOT (1) have NOT (2) is (1) have NOT (2) is NOT A.

B.

C.

D.

Page: 58

59. Unit Two is performing SCCP due to a primary leak causing rising water level in the HPCI and South RHR areas. The following timeline for water levels in these areas is as follows:

Time Event 1300 HPCI area at Max Safe Operating Level.

1305 South RHR area at Max Normal Operating Level 1310 HPCI area lowers to Max Normal Operating Level 1315 South RHR area at Max Safe Operating Level 1320 HPCI area again at Max Safe Operating Level Which one of the following completes both statements below?

IAW SCCP, the earliest time that an Emergency Depressurization is required is at (1).

IAW 0EOP-01-UG, EOP Users Guide, the basis for Emergency Depressurization in this condition is that (2).

(1) 1315 (2) safe shutdown equipment may fail (1) 1315 (2) personnel access to these areas is precluded (1) 1320 (2) safe shutdown equipment may fail (1) 1320 (2) personnel access to these areas is precluded A.

B.

C.

D.

Page: 59

60. During an ATWS on Unit One, plant conditions are:

APRMs Downscale SLC Tank injected (pumps secured)

RPV water level 70 inches, lowering MSL Flow 0.5 Mlbm/hr Drywell ref leg temp 200°F The CRS has directed a RPV pressure band of 700 - 900 psig.

[Reference Provided]

If RPV water level continues to lower, which one of the following completes the statement below IAW ATWS Procedure and 0OI-37.11, Transient Mitigation Guidelines?

Emergency Depressurization must be performed when RPV water level first reaches:

-65 inches

-70 inches

-77.5 inches

-82.5 inches A.

B.

C.

D.

Page: 60

61. Unit One is 100% power.

Unit Two is in MODE 3 with RHR Loop A in SDC with the following indications:

RHR Hx 2A RHR Sys Press 325 psig RHR SW Pump A Disch Press 310 psig Subsequently, UA-03 (5-5), Service Wtr Effluent Rad High, is received.

Which one of the following completes the both statements below?

The radiation detector for the D12-R604, Service Water Rad Monitor, is located (1) of E11-PVD-F068A, Heat Exchanger 2A SW Discharge Vlv.

RRCP (2) required to be entered for this condition.

(1) upstream (2) is (1) upstream (2) is NOT (1) downstream (2) is (1) downstream (2) is NOT A.

B.

C.

D.

Page: 61

62. Unit One is in MODE 3 following a seismic event and reactor scram with the following plant conditions:

Reactor level 55 inches Reactor pressure 500 psig Drywell pressure 9 psig Division I PNS header pressure 93 psig Division II PNS header pressure 98 psig Which one of the following completes both statements below?

Div I Backup N2 Rack Isol Vlv, RNA-SV-5482 is (1).

Div I Non-Inrpt RNA, RNA-SV-5262 is (2).

(1) open (2) open (1) open (2) closed (1) closed (2) open (1) closed (2) closed A.

B.

C.

D.

Page: 62

63. Unit One is operating at 100% power when the following events occur:

LOOP occurs Unit One NSW header ruptures in the Service Water Building All Unit One Service Water pumps supplying the NSW Header are manually tripped.

Which one of the following completes the statement below concerning the Diesel Generators (DG) cooling water supply?

Cooling water for DG1 and (1) will auto transfer to (2).

(1) DG2 (2) Unit One CSW (1) DG2 (2) Unit Two NSW (1) DG3 (2) Unit One CSW (1) DG3 (2) Unit Two NSW A.

B.

C.

D.

Page: 63

64. Which one of the following completes both statements below concerning the operation of the brass handled ASSD keylock switches used in 0ASSD-02, Control Building, Section E, Diesel Generator Actions?

The six switches in a row must be placed in LOCAL (1) placing the seventh switch in LOCAL.

The purpose of this sequence is to prevent a loss of DG2 due to a loss of the redundant power supply fuses for the (2) circuitry.

(1) before (2) output breaker (1) before (2) engine run control (1) after (2) output breaker (1) after (2) engine run control A.

B.

C.

D.

Page: 64

65. Unit Two is operating at 100% power with a grid system disturbance when UA-13 (2-4),

Generator Field Overexcitation, is received due to activation of the inverse time maximum excitation limit relay.

Which one of the following completes both statements below?

IAW 2OP-27, Generator and Exciter System Operating Procedure, the System Load Dispatcher is required to be notified as soon as practical, but within (1), of any change in status of the voltage regulator.

If the condition does not clear, voltage regulation (2) automatically swap to the manual voltage regulator.

(1) 30 minutes (2) will (1) 30 minutes (2) will NOT (1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2) will (1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2) will NOT A.

B.

C.

D.

Page: 65

66. Which one of the following completes both statements below regarding motor operated valves (MOVs)?

IAW AD-OP-ALL-0110, General Equipment Operating Standards, the preferred method for verifying an energized MOV's position is (1).

IAW 0AP-013, Plant Equipment Control, control switches for throttle MOVs shall be held in the CLOSED position for an additional (2) after the full closed indication is received.

(1) control indicating lights (2) 1-5 seconds (1) control indicating lights (2) 10-15 seconds (1) locally at the valve (2) 1-5 seconds (1) locally at the valve (2) 10-15 seconds A.

B.

C.

D.

Page: 66

67. Which one of the following completes both statements below IAW 0AP-013, Plant Equipment Control?

DC Limitorque valves have a specific duty cycle, which is defined as the maximum number of starts in (1).

After the duty cycle for a DC Limitorque valve is exceeded, the motor needs to be allowed to cool for at least (2).

(1) 5 minutes (2) 50 minutes (1) 5 minutes (2) 15 minutes (1) 10 minutes (2) 50 minutes (1) 10 minutes (2) 15 minutes A.

B.

C.

D.

Page: 67

68. IAW AD-OP-ALL-1000, Conduct Of Operations, which one of the following completes both statements below?

(1) plant PA announcement(s) must be made when starting or stopping plant equipment from the main control room.

A PA announcement (2) required for starting TBCCW Pump 2B from the control room.

(1) One (2) is (1) One (2) is NOT (1) Two (2) is (1) Two (2) is NOT A.

B.

C.

D.

Page: 68

69. Which one of the following completes both statements below IAW 2OI-03.4.1, Unit 2 Reactor Operator Daily Check Sheets?

The limit for reactor power averaged over the previous 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, on PPC Screen 850, is < (1).

The limit for reactor pressure, on the Core Mon Printout, is < (2).

(1) 2923 MWT (2) 1030 psia (1) 2923 MWT (2) 1045 psia (1) 2981 MWT (2) 1030 psia (1) 2981 MWT (2) 1045 psia A.

B.

C.

D.

Page: 69

70. Which one of the following completes both statements below IAW Tech Specs Definitions, Table 1.1-1, MODES?

In MODE 3, the MODE switch (1) allowed to be in the Start & Hot S/B position.

In MODE 5, the MODE switch (2) allowed to be in the Shutdown position.

(1) is (2) is (1) is (2) is NOT (1) is NOT (2) is (1) is NOT (2) is NOT A.

B.

C.

D.

Page: 70

71. While performing a pre-job brief, it is discovered that plant conditions are different from the expected conditions for which a procedure was written. The plant conditions are expected to return to normal. The CRS has determined that a temporary procedure change is required.

IAW AD-DC-ALL-0201, Development and Maintenance of Controlled Procedure Manual Procedures, which one of the following completes both statements below in regards to the temporary procedure change?

The electronic copy of the procedure (1) required to be placed on a Change Hold Status.

The expiration date shall not exceed (2) from the interim approval date.

(1) is (2) 7 days (1) is (2) 4 months (1) is NOT (2) 7 days (1) is NOT (2) 4 months A.

B.

C.

D.

Page: 71

72. Unit One is operating at 100% power when the following annunciator is received:

UA-03 (3-3), Turb Bldg Vent Rad High (blue bar)

The CRS has entered RRCP due to Turbine Building Ventilation WRGM indication being at the EAL ALERT level.

Which one of the following completes both statements below?

The normal mode of Turbine Building Ventilation on Unit One is (1).

IF the TB WRGM indication remains at the EAL ALERT level, THEN a reactor scram (2) required.

(1) once-through (2) is (1) once-through (2) is NOT (1) recirculation (2) is (1) recirculation (2) is NOT A.

B.

C.

D.

Page: 72

73. Which one of the following completes both statements below concerning primary containment entry requirements?

IAW 0OI-01.03, Non Routine Activities, Attachment 11, Drywell Entry Requirements, the TIP detectors (1) to be stored at the Indexer.

IAW 0E&RC-0261, Drywell Entry, Drywell entries are NOT allowed when reactor power is above (2).

(1) are required (2) 15%

(1) are required (2) 25%

(1) are NOT allowed (2) 15%

(1) are NOT allowed (2) 25%

A.

B.

C.

D.

Page: 73

74. The Unit One OATC determines that all of the Panel XU-80 annunciators (UA-48, 49, & 50) are inoperable.

IAW 0AOP-29.0, Malfunction of Annunciators, which one of the following completes both statements below?

The reactor building (1) required to be evacuated.

Control Room access (2) required to be restricted.

(1) is (2) is (1) is (2) is NOT (1) is NOT (2) is (1) is NOT (2) is NOT A.

B.

C.

D.

Page: 74

75. During operation at 100% power with the instrument air NOT cross-tied, the following indication is observed:

Assuming the situation continues to degrade at the current rate, which one of the following represents the earliest time that the MSIVs may start drifting closed IAW 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures?

1203 1208 1210 1212 A.

B.

C.

D.

Page: 75