ML17263A604

Final SRO Written as Given and Answer Sheet - Delay Release 2 Yrs

ML17263A604
Person / Time
Site:	Brunswick
Issue date:	08/08/2017
From:	NRC/RGN-II
To:
References
Download: ML17263A604 (102)

Text

Q49 modified to state : "Complete" loss of offsite power.

ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: 08/08/2017 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 provided 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 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam. SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

_______________________________

Applicant's Signature Results RO/SRO-Only/ Total Examination Values ____/ ____ / ____

Applicant's Score ____/ ____ / ____

Points Applicant's Grade ____/ ____ / ____

Percent

1. Unit Two is operating at 100% power, when the 2A Recirc Pump trips.

Which one of the following completes both statements below?

A-05 (4-8), OPRM TRIP ENABLED, (yellow bar) (1) be in alarm.

IAW 2AOP-04.0, Low Core Flow, reactor power must be reduced to less than (2) power.

A. (1) will (2) 50%

B. (1) will (2) 60%

C. (1) will NOT (2) 50%

D. (1) will NOT (2) 60%

Page: 1 of 100 7/5/2017

2. An electrical transient occurred with the following annunciators in alarm:

UA-15 (2-4), BUS E1 TO SUB E5 BKR TRIP UA-15 (3-4), SUB E5 XFMR TEMP HIGH/480V GROUND A field operator has reported local transformer peak winding temperature on Bus E5 was 150°C.

Which one of the following completes both statements below?

Bus E5 has de-energized due to (1) .

480V Bus E5 has the capability to be cross-tied to 480V Bus (2) .

A. (1) a transformer fault (2) E6 B. (1) a transformer fault (2) E7 C. (1) high transformer temperature (2) E6 D. (1) high transformer temperature (2) E7 Page: 2 of 100 7/5/2017

3. Unit One is at 100% power and the CRS has directed entry into 0AOP-39.0, Loss of DC Power, due to DC Switchboard 1B Breaker GL6, Feeder for 125 VDC Panel 1B, tripping open.

Which one of the following completes both statements below?

The (1) DC control power supply for DG2 has been de-energized.

IAW 0AOP-39.0, DG2 DC control power transfer is locally performed at the (2) .

A. (1) normal (2) DC Distribution Panels B. (1) normal (2) DG2 Excitation Control Panel C. (1) alternate (2) DC Distribution Panels D. (1) alternate (2) DG2 Excitation Control Panel Page: 3 of 100 7/5/2017

4. Unit One is at 104 MWe performing 0GP-05, Unit Shutdown.

Subsequently, the Unit One Bypass Valves fail as-is.

Which one of the following completes both statements below?

A-05 (3-5), REACTOR VESS HI PRESS, (yellow bar) will first alarm when pressure reaches (1) psig.

If the Emergency Trip System Trip pushbutton is depressed IAW 1OP-26, Turbine System Operating Procedure, the initial plant response is a(n) (2) in core power.

A. (1) 1050 (2) decrease B. (1) 1050 (2) increase C. (1) 1060 (2) decrease D. (1) 1060 (2) increase Page: 4 of 100 7/5/2017

5. Following an automatic reactor scram the crew is evaluating whether the reactor will remain shut down under all conditions without boron.

Which one of the following completes both statements below?

IAW 0OI-37.13, EOP Cautions and Tables Basis Document, the Maximum Subcritical Banked Withdrawal Position (MSBWP), position (1) , is the greatest banked rod position for all rods at which the reactor will remain shutdown under all conditions If the MSBWP is met for all control rods, then EOP-01-LEP-02, Alternate Control Rod Insertion, (2) required to be performed in order to reset the scram.

A. (1) 00 (2) is B. (1) 00 (2) is NOT C. (1) 02 (2) is D. (1) 02 (2) is NOT Page: 5 of 100 7/5/2017

6. Which one of the following identifies why ASSD procedures direct the Normal/Local switches for the RHR equipment to be placed in Local?

A. To ensure automatic actuation of RHR remains available.

B. To prevent spurious operation/actuation of RHR components.

C. To prevent overloading DGs during spurious operation of RHR pumps.

D. To ensure divisional separation of RHR equipment required for safe shutdown.

Page: 6 of 100 7/5/2017

7. A reactor scram was inserted on Unit Two due to a complete loss of RBCCW.

IAW 0AOP-16.0, RBCCW System Failure, which one of the following identifies the maximum time the CRD Pumps are allowed to be operated?

A. 1.5 minutes B. 10 minutes C. 20 minutes D. 30 minutes Page: 7 of 100 7/5/2017

8. IAW 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures, which one of the following completes the statement below ?

As PNS header pressure lowers, the Backup Nitrogen system (1) be aligned and will ensure a pneumatic supply is maintained to the (2) .

A. (1) will automatically (2) SRVs B. (1) will automatically (2) MSIVs C. (1) requires manual action to (2) SRVs D. (1) requires manual action to (2) MSIVs Page: 8 of 100 7/5/2017

9. Alternate shutdown cooling using SRVs has been established. Plant conditions are:

RHR Loop A in torus cooling RHR Loop B injecting to the reactor Reactor pressure 115 psig SRV B21-F013G open It becomes desired to make an adjustment to lower the cool down rate.

[Reference Provided]

Which one of the following completes the statement below?

This can be accomplished by closing B21-F013G and opening SRV:

A. B21-F013A.

B. B21-F013J.

C. B21-F013K.

D. B21-F013L.

Page: 9 of 100 7/5/2017

10. Unit Two is in a refueling outage with the fuel pool gates installed.

Subsequently, A-04 (6-7), FUEL POOL COOLING ALARM, alarms IAW 0AOP-38.0, Loss of Fuel Pool Cooling, which one of the following completes both statements below?

An entry condition into SCCP will first be required when Spent Fuel Pool water temperature exceeds (1) .

0AOP-38.0 directs the use of (2) to maintain Unit Two Spent Fuel Pool Water Temperature within a specified band.

A. (1) 125°F (2) Supplemental Spent Fuel Pool Cooling System B. (1) 150°F (2) Supplemental Spent Fuel Pool Cooling System C. (1) 125°F (2) Alternate Decay Heat Removal System D. (1) 150°F (2) Alternate Decay Heat Removal System Page: 10 of 100 7/5/2017

11. Unit Two is executing PCCP with the following conditions:

Drywell temperature: 310°F Reactor pressure: 800 -1000 psig Torus level: -6 inches Torus pressure: 30 psig Torus temperature: 160°F

[Reference Provided]

Which one of the following identifies the reason an emergency depressurization is required?

A. Drywell temperature has exceeded the design SRV solenoid temperature.

B. Torus Level has exceeded the SRV tail pipe level limit.

C. Torus temperature has exceeded HCTL.

D. Torus pressure has exceeded the PSP.

Page: 11 of 100 7/5/2017

12. Initial Conditions:

A spurious Group 1 isolation occurred on Unit One Pressure peaked at 1135 psig before decreasing Pressure decreased to 870 psig before rising Current Conditions:

SRVs are being manually operated IAW the EOPs Reactor power is 13.8%

Reactor pressure is stable at 1000 psig Torus pressure is 5.3 psig Which one of the following completes both statements below?

(1) SRVs are currently open to maintain reactor pressure stable at 1000 psig.

For the currently open SRVs, the SRV tailpipe temperature recorder, 1-B21-TR614, will read approximately (2) .

A. (1) Two (2) 300°F B. (1) Two (2) 550°F C. (1) Four (2) 300°F D. (1) Four (2) 550°F Page: 12 of 100 7/5/2017

13. Unit Two is at 75% power with HPCI testing in progress IAW 0PT-9.2, HPCI System Operability Test.

Suppression Pool temperatures were recorded at the following times:

Time Temperature 1300 97° F 1500 107° F Which one of the following completes both statements below?

The earliest time UA-12 (5-4), SPTMS DIV I BULK WTR TEMP SETPOINT TS1, (blue bar) annunciated was at (1) .

Based on the conditions at time 1300, entry into PCCP (2) required.

A. (1) 1300 (2) is B. (1) 1300 (2) is NOT C. (1) 1500 (2) is D. (1) 1500 (2) is NOT Page: 13 of 100 7/5/2017

14. Following a small break LOCA on Unit Two, drywell sprays have been secured.

Current plant conditions are:

Drywell pressure 8 psig RPV water level 187 inches Reactor pressure 300 psig Torus water level -20 inches Drywell average air temperature 280°F and rising

[Reference Provided]

Which one of the following completes both statements below?

IAW PCCP the first drywell temperature threshold that requires initiation of drywell sprays is before reaching (1) .

IAW 0EOP-01-SEP-02, Drywell Spray Procedure, drywell sprays (2) allowed to be re-initiated.

A. (1) 300° F (2) are B. (1) 300° F (2) are NOT C. (1) 340° F (2) are D. (1) 340° F (2) are NOT Page: 14 of 100 7/5/2017

15. Following a LOCA on Unit Two, plant conditions are as follows:

Reactor water level 50 inches and rising Reactor pressure 140 psig Torus temperature 220°F Torus pressure 10.5 psig on CAC-PI-1257-2A Torus level -43 inches 2A CS pump flow 5000 gpm 2B RHR pump flow 5000 gpm

[Reference Provided]

Which one of the following completes both statements below?

2A Core Spray pump (1) operating within NPSH limits.

2B RHR pump (1) operating within NPSH limits.

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: 15 of 100 7/5/2017

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

Reactor water level -35 inches, lowering Reactor pressure 900 psig Drywell ref leg temp 185°F Injection sources None available

[Reference Provided]

IAW 0EOP-01-UG, User's Guide, which one of the following is the lowest RPV water level for the above conditions that still assures adequate core cooling is being maintained?

A. -55 inches B. -70 inches C. -72.5 inches D. -82.5 inches Page: 16 of 100 7/5/2017

17. Unit Two has experienced an ATWS with the following conditions:

SLC has been initiated Control Rods 22-23 and 10-19 are at position 48 10 control rods are at position 02 All other control rods are at position 00 The following sequence of events has occurred in the order listed:

Event 1 Control Rod 22-23 is at position 00 Event 2 APRM downscale indication lights are lit Event 3 Control Rod 10-19 is at position 02 Event 4 SLC has injected into the RPV to a tank level of 0%

IAW the ATWS procedure, which one of the following identifies the earliest event where actions to cooldown and depressurize the RPV may proceed?

A. Event 1 B. Event 2 C. Event 3 D. Event 4 Page: 17 of 100 7/5/2017

18. Unit Two has entered RRCP due to fuel failure which has resulted in a high offsite release.

Which one of the following completes both statements below?

CREV will automatically start in the recirculation mode when Control Room Area Radiation Monitor (Channel 1) first exceeds (1) .

CREV operation in the recirculation mode is required to maintain habitability of the (2) .

A. (1) 1 mR/hr (2) Control Room Envelope B. (1) 1 mR/hr (2) entire Control Building C. (1) 7 mR/hr (2) Control Room Envelope D. (1) 7 mR/hr (2) entire Control Building Page: 18 of 100 7/5/2017

19. The following sequence of reports have been received on Unit One:

0800 A report of smoke from the Service Water Building.

0807 Fire Brigade members have commenced using a fire extinguisher on a minor electrical fire on the Service Water Building pump 20 EL area.

0810 Fire Brigade members have transitioned to using a hose reel and are applying a water fog to the fire.

0815 The fire is out with re-flash watch stationed.

Which one of the following completes both statements below?

IAW 0PFP-PBAA, Power Block Auxiliary Areas Pre-Fire Plans (SW, RW, AOG, TY, EY, PDC, DGS, MCP), the appropriate fire extinguisher to use to attack the fire at 0807 would be a(n) (1) extinguisher.

IAW 0PFP-013, General Fire Plan, the earliest time that the Reactor Operator is required to request "911" off-site assistance is at (2) .

A. (1) AFFF (2) 0807 B. (1) AFFF (2) 0810 C. (1) CO2 (2) 0807 D. (1) CO2 (2) 0810 Page: 19 of 100 7/5/2017

20. Initial Conditions:

Unit One is operating at 95% power A grid alert has been issued due to high electric demand Subsequently:

UA-06 (1-2), GEN UNDER FREQ RELAY, alarms Grid frequency, as read on 1-GEN-FM-736, is 59.1 Hz Which one of the following completes both statements below?

The auto actions of UA-06 (1-2) states, generator MWs (1) increase to the limits of pressure set.

IAW 0AOP-22.0, Grid Instability, a reactor manual scram is required (2) .

A. (1) will (2) immediately B. (1) will (2) within five minutes C. (1) will NOT (2) immediately D. (1) will NOT (2) within five minutes Page: 20 of 100 7/5/2017

21. Which one of the following identifies the value of TAF with Unit One reactor pressure at 30 psig?

A. -7.5 inches B. -10 inches C. -17.5 inches D. -20 inches Page: 21 of 100 7/5/2017

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

Entry into RRCP is first required when the offsite gaseous release rate is above the (1) EAL as specified in RRCP Table M-4.

IAW 0ERP, Radiological Emergency Response Plan, wind direction determines the proper Plume Exposure Emergency Planning Zone (EPZ) for shelter/evacuation within a (2) mile radius of the Brunswick plant.

A. (1) Alert (2) 10 B. (1) Alert (2) 50 C. (1) Site Area Emergency (2) 10 D. (1) Site Area Emergency (2) 50 Page: 22 of 100 7/5/2017

23. Unit One is operating at 100% power.

Which one of the following completes both statements below in response to a trip of the 1A RPS MG set?

The Reactor Building Roof effluent flow will (1) .

Entry into SCCP based on reactor building negative pressure, (2) required.

A. (1) lower (2) is B. (1) lower (2) is NOT C. (1) rise (2) is D. (1) rise (2) is NOT Page: 23 of 100 7/5/2017

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

IAW PCCP, with torus water level rising, a reactor scram is required before level first reaches the:

A. bottom of the ring header B. torus downcomer opening C. suppression chamber to drywell vacuum breakers D. reactor building to suppression chamber vacuum breakers Page: 24 of 100 7/5/2017

25. Unit Two is operating at 100% power when UA-3 (6-2), RX BLDG VENT TEMP HIGH (red bar) alarms.

Which one of the following completes both statements below?

The reactor building ventilation system (1) tripped and isolated.

This alarm indicates that the (2) are approaching their environmental qualification temperatures.

A. (1) has (2) RB Ventilation radiation monitors B. (1) has (2) RB Isolation Damper solenoid valves C. (1) has NOT (2) RB Ventilation radiation monitors D. (1) has NOT (2) RB Isolation Damper solenoid valves Page: 25 of 100 7/5/2017

26. Unit Two is operating at 100% power with ONLY the following indications noted:

UA-03 (2-3), RX BLDG ROOF VENT RAD HIGH (blue bar) is in alarm.

UA-03 (2-7), AREA RAD RX BLDG HIGH (blue bar) is in alarm.

The 2-CAC-AQH-1264-3, Reactor Bldg Vent Noble Gas Monitor is indicating 50 mR/hr and slowly rising.

Area Radiation Monitor Panel (P-600),

Channel 30, is indicating as shown.

Which one of the following completes both statements below?

The Reactor Building Ventilation System (1) currently isolated.

ARM Channel 2-30 is reading (2) .

A. (1) is (2) 15 MR/HR B. (1) is (2) 50 MR/HR C. (1) is NOT (2) 15 MR/HR D. (1) is NOT (2) 50 MR/HR Page: 26 of 100 7/5/2017

27. Initial Conditions:

Unit One has had a complete loss of RBCCW Following a manual reactor scram, the Scram Discharge Volume (SDV) ruptured Current conditions:

Drywell pressure 2.3 psig Drywell average temperature 190°F Rx Bldg 20 ft south temperature 195°F UA-12 (1-3), SOUTH CS RM FLOOD LEVEL HI-HI, (red bar) is in alarm UA-12 (1-4), SOUTH RHR RM FLOOD LEVEL HI-HI, (red bar) is in alarm Which one of the following identifies the operator action required by SCCP?

A. Reset RPS to isolate the primary system discharge.

B. Commence a reactor cooldown not to exceed 100°F/hr C. Rapidly depressurize to the main condenser irrespective of cooldown rate D. Perform an emergency depressurization Page: 27 of 100 7/5/2017

28. Unit One is in MODE 4 with the following conditions:

Loop A RHR is in Standby, aligned for LPCI Injection Loop B RHR is in Shutdown Cooling with the 1B RHR Pump in service Subsequently, 1A MG set trips.

Which one of the following completes both statements below?

The Shutdown Cooling valve that has closed is the (1) .

Subsequently, if level lowers to LL3, the E11-F015A, Inboard Injection Valve, (2) automatically open.

A. (1) E11-F008, RHR Shutdown Cooling Otbd Isolation Valve (2) will NOT B. (1) E11-F009, RHR Shutdown Cooling Inbd Isolation Valve (2) will NOT C. (1) E11-F008, RHR Shutdown Cooling Otbd Isolation Valve (2) will D. (1) E11-F009, RHR Shutdown Cooling Inbd Isolation Valve (2) will Page: 28 of 100 7/5/2017

29. Which one of the following identifies the 4160V power supply to RHR Pump 1C?

A. E1 B. E2 C. E3 D. E4 Page: 29 of 100 7/5/2017

30. Unit Two is in the EOPs with the following conditions:

HPCI is operating post-scram in pressure control mode with the HPCI Flow Controller in Automatic RPV level, temperature, and pressure are stable at expected values Subsequently, E41-F012, Minimum Flow Bypass To Suppression Pool Valve, fails full-open Which one of the following identifies RPV pressure response after new steady-state conditions are reached, and why?

A. Pressure will be lower, because the flow controller will sense lower flow and speed up the HPCI turbine.

B. No change in pressure, because the flow controller is not affected by E41-F012 inadvertently opening.

C. No change in pressure, because the HPCI turbine speed controller will maintain a constant turbine RPM.

D. Pressure will be higher, because the flow controller will sense higher flow and slow down the HPCI turbine.

Page: 30 of 100 7/5/2017

31. Unit One is in MODE 5 with both RHR Loops declared INOPERABLE.

IAW Tech Spec 3.5.2, ECCS-Shutdown, which one of the following completes both statements below?

With the spent fuel pool gates installed, a minimum of (1) Core Spray subsystem(s) shall be OPERABLE.

With the spent fuel storage pool gates removed, a water level greater than or equal to a minimum of (2) over the top of the reactor pressure vessel flange is required to exit the mode of APPLICABILITY for LCO 3.5.2.

A. (1) one (2) 19 feet 11 inches B. (1) one (2) 21 feet 10 inches C. (1) two (2) 19 feet 11 inches D. (1) two (2) 21 feet 10 inches Page: 31 of 100 7/5/2017

32. Unit One is in MODE 3 when a steam line rupture occurs in the drywell.

One minute following the rupture, the following conditions exist:

Drywell pressure 10 psig Reactor pressure 360 psig Reactor water level 55 inches Which one of the following completes both statements below?

The E21-F004A, Outboard Injection Vlv, and E21-F005A, Inboard Injection Vlv, are (1) .

The shutoff head of the Core Spray pumps is approximately (2) .

A. (1) closed (2) 200 psig B. (1) closed (2) 300 psig C. (1) open (2) 200 psig D. (1) open (2) 300 psig Page: 32 of 100 7/5/2017

33. Unit Two was operating at 100% power when the following sequence of events occur:

Time Event 1200 MCC 2XG tagged out of service 1302 An ATWS occurs on Unit Two 2-C41-CS-S1, SLC PUMPS A & B, is placed in PUMP B RUN position 1303 SLC PUMP 2A red light OUT SLC PUMP 2B red light LIT SLC A SQUIB VALVE CONTINUITY yellow light OUT SLC B SQUIB VALVE CONTINUITY yellow light LIT 1305 2-C41-CS-S1, SLC PUMPS A & B, is placed in PUMP A&B RUN position.

Which one of the following completes both statements below?

At 1304, the SLC system (1) injecting into the reactor vessel.

At 1306, the SLC system (2) .

A. (1) is (2) flow rate into the reactor vessel has increased B. (1) is NOT (2) has begun to inject into the reactor vessel C. (1) is (2) flow rate into the reactor vessel has NOT increased D. (1) is NOT (2) flow rate into the reactor vessel has NOT increased Page: 33 of 100 7/5/2017

34. The status of the ARI switches on Unit Two are as follows:

Which one of the following completes the statement below?

(1) of the control rods inserted because (2) of the ARI solenoid valves have repositioned.

A. (1) All (2) all B. (1) Some (2) ONLY half C. (1) None (2) none D. (1) None (2) ONLY half Page: 34 of 100 7/5/2017

35. A startup is being conducted on Unit Two with the following conditions:

The reactor is critical with SRM/IRM overlap having just been confirmed All SRMs are reading between 5x103 and 1x104 cps All IRMs are reading between 35 and 45 on Range 1 The operator has inadvertently selected both the SRMs and the IRMs for withdraw Which one of the following Control Rod Blocks will be the first automatic action to occur as the detectors are withdrawn?

A. SRM Downscale B. IRM Downscale C. SRM Retract Permissive D. IRM Detector Not Full In Page: 35 of 100 7/5/2017

36. Which one of the following distribution systems provides power to the Source Range Monitor (SRM) detectors and signal processing circuitry?

A. 24/48 VDC B. 125/250 VDC C. 120 VAC Emergency Power System D. 120 VAC Uninterruptible Power Supply Page: 36 of 100 7/5/2017

37. Unit Two is operating at 100% power.

Which one of the following identifies a plant transient that will cause the APRM ODA displays to automatically shift to the stability screen?

A. Control rod 46-15 drifts fully into the core.

B. Inadvertant initiation of HPCI with injection.

C. 2-FW-V120, FW HTRS 4&5 BYP VLV, opens.

D. Recirculation Pump A trips.

Page: 37 of 100 7/5/2017

38. Unit One is operating at 100% power with APRM 1 bypassed.

Subsequently, a critical self-test fault occurs on APRM 3.

Which one of the following completes both statements below?

RBM Channel A reference signals are currently from (1) .

RBM Channel B reference signals are currently from (2) .

A. (1) APRM 2 (2) APRM 2 B. (1) APRM 2 (2) APRM 4 C. (1) APRM 4 (2) APRM 2 D. (1) APRM 4 (2) APRM 4 Page: 38 of 100 7/5/2017

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

Demineralized Water Keep Fill System is connected to the RCIC System (1) .

Following a Loss of Offsite Power to both Units, the (2) will assure RCIC System protection against water hammer.

A. (1) suction line (2) 2-E51-V70, RCIC Keepfill Station Bypass Valve B. (1) suction line (2) 2-E51-F014, RCIC Pump Discharge Check Valve C. (1) discharge line (2) 2-E51-V70, RCIC Keepfill Station Bypass Valve D. (1) discharge line (2) 2-E51-F014, RCIC Pump Discharge Check Valve Page: 39 of 100 7/5/2017

40. Unit Two was operating at 100% power when a rupture in the Recirculation Loop B occurred.

RHR Pump A Running with discharge pressure of ~225 psig RHR Pump D OFF RHR Pumps B / C Unavailable CS Pump A Running with discharge pressure of ~360 psig CS Pump B Unavailable Reactor water level 110 inches and lowering rapidly ADS NOT inhibited Which one of the following predicts the response of the ADS system?

A. ADS will initiate in 83 seconds, the timer is now timing.

B. ADS will initiate in 83 seconds after RHR Pump D is started.

C. ADS will initiate in 83 seconds after reactor water level lowers to 105 inches.

D. ADS will initiate in 83 seconds after reactor water level lowers to 45 inches.

Page: 40 of 100 7/5/2017

41. With both units at 100% power, a Main Control Room evacuation has been initiated IAW 0AOP-32.0, Plant Shutdown from Outside Control Room.

Immediate actions were NOT performed by the crew prior to evacuation.

Which one of the following completes the statement below IAW 0AOP-32.0?

(1) SRVs will be cycled remotely to maintain reactor pressure.

SRVs should be left open for a minimum of (2) or until a 150 psi decrease in reactor pressure has occurred to minimize the number of SRV openings.

A. (1) ADS (2) one minute B. (1) ADS (2) three minutes C. (1) Non-ADS (2) one minute D. (1) Non-ADS (2) three minutes Page: 41 of 100 7/5/2017

42. With Unit Two operating at 50% power, which one of the following completes both statements below?

High Steam Flow sensed (on all detectors) in one main steam line (1) result in a full MSIV closure signal.

If a full MSIV closure signal were received and the initiating condition had cleared, the MSIV isolation signal logic (2) be reset with the MSIV control switches at the RTGB in the OPEN position.

A. (1) will (2) can B. (1) will (2) can NOT C. (1) will NOT (2) can D. (1) will NOT (2) can NOT Page: 42 of 100 7/5/2017

43. Unit One has been at 20% for the past 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Which one of the following completes both statements below?

The current pneumatic supply for Safety Relief Valves is from (1) .

If the pneumatic supply is lost, the Safety Relief Valve accumulators are designed to ensure each valve can cycle (2) time(s).

A. (1) RNA, Reactor Non-Interruptible Air (2) one B. (1) RNA, Reactor Non-Interruptible Air (2) at least five C. (1) PNS, Pneumatic Nitrogen System (2) one D. (1) PNS, Pneumatic Nitrogen System (2) at least five Page: 43 of 100 7/5/2017

44. A Unit One startup is in progress IAW 0GP-02, Approach to Criticality and Pressurization of the Reactor.

Operators are currently performing 1OP-32, Condensate and Feedwater System Operating Procedure, Section 6.1.5, Reactor Feed pump Operation from Idle Speed to Injection at Low Pressure Conditions.

Current plant conditions are:

RFPT A Speed Controller in MANUAL RFPT speed at 2550 rpm RFPT A discharge pressure 100 psig higher than reactor pressure Feedwater Control Mode Select Switch in 1 ELEM RFPT A MAN/DFCS control switch in MAN IAW 1OP-32, Section 6.1.5, which one of the following completes both statements below?

When the RFPT A MAN/DFCS control switch is selected to DFCS, the (1) will control RFPT speed.

Following the DFCS selection performed above, if the DFCS control signal lowers to 2400 rpm, the (2) will maintain RFPT speed.

A. (1) C32-SIC-R600, Master RFPT Speed/Reactor Level Controller (2) Woodward 5009 digital control B. (1) C32-SIC-R600, Master RFPT Speed/Reactor Level Controller (2) C32-SIC-R601A, RFPT A Speed Controller C. (1) C32-SIC-R601A, RFPT A Speed Controller (2) Woodward 5009 digital control D. (1) C32-SIC-R601A, RFPT A Speed Controller (2) C32-SIC-R601A, RFPT A Speed Controller Page: 44 of 100 7/5/2017

45. Which one of the following completes both statements below concerning the HPCI Barometric Condenser Vacuum Pump?

The pump (1) automatically start from the HPCI initiation signal.

The pump discharges to the (2) .

A. (1) will (2) SBGT B. (1) will (2) Torus C. (1) will NOT (2) SBGT D. (1) will NOT (2) Torus Page: 45 of 100 7/5/2017

46. During accident conditions on Unit Two the following sequence of events occur:

Time (seconds) Event 0 Drywell pressure rises above the scram setpoint 2 Complete Loss of Off-site Power occurs 8 Reactor pressure is 400 psig 10 DGs energize their respective E Buses 15 Reactor water level drops below LL3 Which one of the following identifies the earliest time that the RHR pumps will auto start?

A. 10 seconds B. 15 seconds C. 20 seconds D. 25 seconds Page: 46 of 100 7/5/2017

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

The Stack Radiation Monitor is capable of being provided with Uninterruptible Power Supply (UPS) power using a/an (1) transfer device.

With the Stack Rad Monitor Power Transfer Switches in the NORM position, (2) UPS is supplying power to the Stack Radiation Monitor.

A. (1) automatic (2) Unit One B. (1) automatic (2) Unit Two C. (1) manual (2) Unit One D. (1) manual (2) Unit Two Page: 47 of 100 7/5/2017

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

Upon a loss of Unit One 125VDC Distribution Panel 3A, a loss of the (1) flow controller indication and annunciation of (2) will occur.

A. (1) HPCI (2) A-01 (1-6), CORE SPRAY SYS I LOGIC PWR FAILURE B. (1) HPCI (2) A-04 (1-8), STM LINE LOW PRESS A C. (1) RCIC (2) A-01 (1-6), CORE SPRAY SYS I LOGIC PWR FAILURE D. (1) RCIC (2) A-04 (1-8), STM LINE LOW PRESS A Page: 48 of 100 7/5/2017

49. DG2 is 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.

DG2 is loaded to 3700 kW.

Subsequently, Unit Two experiences a Loss of Offsite Power (LOOP)

Which one of the following completes both statements below?

DG2 output breaker will (1) .

When restoring off-site power back onto Bus E2, prior to transferring DG2 from AUTO to MANUAL, DG2 frequency will be required to be (2) .

A. (1) remain closed (2) raised B. (1) remain closed (2) lowered C. (1) open and reclose (2) raised D. (1) open and reclose (2) lowered Page: 49 of 100 7/5/2017

50. Unit Two is operating at 100% power with the following conditions:

Unit One and Unit Two Service Air Systems are cross-tied 2D Service Air Compressor is the lead compressor 2A Air Dryer in service Subsequently, Control power for the 2A Air Dryer is lost UA-1 (5-3) AIR DRYER 2A TROUBLE is in ALARM Which one of the following completes both statements below?

The loss of control power to Air Dryer 2A will result in (1) .

IAW UA-01 (5-3), the crew is required to (2) .

A. (1) continued air flow through one tower of Air Dryer 2A (2) place Service Air Dryer 1B in service and remove 2A from service B. (1) continued air flow through one tower of Air Dryer 2A (2) consider swapping 1D Service Air Compressor into lead C. (1) 2-SA-PV-5067, Service Air Dryer Bypass Pressure Control Valve, opening (2) place Service Air Dryer 1B in service and remove 2A from service D. (1) 2-SA-PV-5067, Service Air Dryer Bypass Pressure Control Valve, opening (2) consider swapping 1D Service Air Compressor into lead Page: 50 of 100 7/5/2017

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

With a loss of the Station Air Compressors, RNA-SV-5481, Division II Backup N2 Rack Isolation Valve, will automatically actuate when instrument air pressure first lowers to less than:

A. 105 psig B. 100 psig C. 98 psig D. 95 psig Page: 51 of 100 7/5/2017

52. Unit One is operating at 100% power when a malfunction in a running Conventional Service Water (CSW) pump motor causes CSW system pressure to start lowering.

Which one of the following completes both statements below?

The highest CSW system pressure that will cause an automatic start signal to be generated for the standby CSW pump is (1) .

If CSW system pressure remains below the pressure setpoint selected above for a minimum of (2) , then SW-V3(V4), SW TO TBCCW HXS OTBD(INBD) ISOL, will reposition to their throttled positions.

A. (1) 65 psig (2) 30 seconds B. (1) 65 psig (2) 70 seconds C. (1) 40 psig (2) 30 seconds D. (1) 40 psig (2) 70 seconds Page: 52 of 100 7/5/2017

53. Unit Two is operating at 100% power with the following RBCCW switch positions:

Subsequently:

E3 Feeder Breaker (Master Breaker), 2-2D-AD1, inadvertently trips DG3 fails to auto-start Which one of the following completes both statements below three minutes after the breaker trip?

RBCCW Pump 2B (1) running.

RBCCW Pump 2C (1) running.

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: 53 of 100 7/5/2017

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

Alternate Rod Insertion (ARI) solenoids are powered from (1) and (2) to actuate.

A. (1) 120 VAC (2) de-energize B. (1) 120 VAC (2) energize C. (1) 125 VDC (2) de-energize D. (1) 125 VDC (2) energize Page: 54 of 100 7/5/2017

55. Which one of the following completes both statements below concerning the CRD mechanism system?

Control rod blades (1) provide enough excess negative reactivity to shutdown the reactor with the two highest worth control rods fully withdrawn.

The peak fuel enthalpy during a control rod drop accident is limited to a maximum of (2) .

A. (1) will (2) 280 cal/g B. (1) will (2) 425 cal/g C. (1) will NOT (2) 280 cal/g D. (1) will NOT (2) 425 cal/g Page: 55 of 100 7/5/2017

56. Unit One is at 100% power with I/C technicians performing a reactor water level instrument surveillance.

Subsequently, I/C inadvertently causes a downscale failure of the, 1-B21-LTS-N031A-4 and C-4, Level Transmitter Slave Trip Units (Reactor Vessel Water Level - Low) which results in the following:

A-01 (1-8), RHR SYS I ACTUATED, (red bar) alarming RHR Pumps 1A and 1C running Which one of the following completes both statements below?

The 1-B32-F031A, (Recirculation) Pump A Disch Vlv, (1) received an isolation signal.

The purpose of the 1-B32-F031A isolation signal is to (2) .

A. (1) has (2) ensure RHR pumps inject into the core region through the jet pumps to provide maximum core cooling B. (1) has (2) prevent damage to the recirc pump thrust bearings due to reverse flow through the idle pump during RHR injection C. (1) has NOT (2) ensure RHR pumps inject into the core region through the jet pumps to provide maximum core cooling D. (1) has NOT (2) prevent damage to the recirc pump thrust bearings due to reverse flow through the idle pump during RHR injection Page: 56 of 100 7/5/2017

57. Unit One is at 50% power with control rod 02-19 currently selected when the following Rod Block Monitor (RBM) timeline of events occur:

1000: RBM B indicates receipt of a non-critical self-test fault 1005: A-06 (4-7), RBM DOWNSCALE/ TROUBLE is illuminated and RBM A flux indicates 2% and stable 1010: RBM A watchdog timer has timed out 1015: RBM B critical self-test fault is received There are no rod movements in progress.

Which one of the following identifies the earliest time annunciator A-05 (2-2), ROD OUT BLOCK, (yellow bar) will be in alarm?

A. 1000 B. 1005 C. 1010 D. 1015 Page: 57 of 100 7/5/2017

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

The TIP system isolation signal is from the (1) Primary Containment Group Isolation Logic.

The TIP Ball Valve (2) a Primary Containment Isolation Valve (PCIV).

A. (1) Inboard (2) is B. (1) Inboard (2) is NOT C. (1) Outboard (2) is D. (1) Outboard (2) is NOT Page: 58 of 100 7/5/2017

59. Fuel movements are in progress on Unit One with the following signal/conditions:

Reactor MODE switch is in REFUEL Main hoist is full up Hoists are NOT loaded All rods are NOT full in BRIDGE NEAR/OVER REACTOR VESSEL (LS1) is actuated Which one of the following completes both statements below?

A Rod Block (1) in effect.

FUEL HOIST INTERLOCK (2) actuated.

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: 59 of 100 7/5/2017

60. Unit One is in MODE 2 with the following conditions:

HP Turbine Shell Warming is in progress IAW 1OP-26,Turbine System Operating Procedure.

The Chest/Shell Warming potentiometer has just been rotated as shown.

The Chest/Shell Warming Selector OFF light has gone out.

IAW 1OP-26, which one of the following completes both statements below?

The Chest/Shell Warming potentiometer (1) require further adjustment in order for steam to be admitted to the HP turbine.

The Chest/Shell Warming potentiometer is rotated in the (2) direction to raise HP Turbine shell pressure.

A. (1) does (2) clockwise B. (1) does (2) counter-clockwise C. (1) does NOT (2) clockwise D. (1) does NOT (2) counter-clockwise Page: 60 of 100 7/5/2017

61. Unit Two is at 23% power with main turbine roll in progress IAW 2OP-26, Turbine System Operating Procedure. Turbine speed is 900 RPM and slowly rising.

The following turbine journal bearing vibration readings are observed on TSI-XR-640:

Bearing #1 5 mils Bearing #6 10 mils Bearing #2 5 mils Bearing #7 11 mils Bearing #3 6 mils Bearing #8 13 mils Bearing #4 7 mils Bearing #9 11 mils Bearing #5 8 mils Bearing #10 10 mils Which one of the following:

1) predicts the plant response and

2) identifies required operator action(s), if any, IAW 2OP-26?

A. (1) An automatic turbine trip will occur.

(2) Manually scram the reactor.

B. (1) An automatic turbine trip will occur.

(2) The reactor is NOT required to be manually scrammed.

C. (1) An automatic turbine trip will NOT occur.

(2) Manually scram the reactor and then trip the turbine.

D. (1) An automatic turbine trip will NOT occur.

(2) Manually trip the turbine, the reactor is NOT required to be manually scrammed.

Page: 61 of 100 7/5/2017

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

DC Distribution Panel 10A provides control power for Condensate Pumps (1) .

4160 VAC Bus 2D supplies power to Condensate Pump (2) .

A. (1) 2A and 2C ONLY (2) 2A B. (1) 2A and 2C ONLY (2) 2B C. (1) 2A, 2B and 2C (2) 2A D. (1) 2A, 2B and 2C (2) 2B Page: 62 of 100 7/5/2017

63. IAW 1OP-32, Condensate and Feedwater System Operating Procedure, which one of the following completes the statement below?

Reactor power is limited to a maximum continuous power of (1) with one reactor feed pump in service to limit reactor feed pump (2) .

A. (1) 60%

(2) runout B. (1) 80%

(2) runout C. (1) 60%

(2) turbine exhaust drain casing level D. (1) 80%

(2) turbine exhaust drain casing level Page: 63 of 100 7/5/2017

64. Consider a loss of AC power supply to the Area Radiation Monitors (ARMs) in the following locations:

Unit One Turbine Building control access corridor Unit One Feedwater Heater Bay access corridor Service Building electrical equipment room E/W corridor Which one of the following completes the statement below?

The ARM local display will indicate (1) which (2) produce a MCR alarm.

A. (1) downscale (2) will B. (1) downscale (2) will NOT C. (1) upscale (2) will D. (1) upscale (2) will NOT Page: 64 of 100 7/5/2017

65. Which one of the following identifies the operation of the Diesel Fire Pump starting system due to an auto start signal?

A. Power from two banks of batteries is used simultaneously to crank the engine.

B. Only one bank of batteries is normally selected, and if the engine does not start after 15 seconds of cranking, the starting controller automatically selects the other bank.

C. Only one bank of batteries is normally selected, and if the engine does not start after 15 seconds of cranking, an operator must locally select the other bank.

D. Only one bank of batteries is physically connected to the starting controller at any given time. The other bank is an installed spare and would require Electrical Maintenance to land leads.

Page: 65 of 100 7/5/2017

66. IAW AD-HU-ALL-0004, Procedure and Work Instruction Use and Adherence, which one of the following completes both statements below concerning Reference Use procedures?

The procedure (1) required to be at the jobsite.

Signoff steps are required to be signed (2) .

A. (1) is (2) as frequently as practical B. (1) is (2) after each step is performed C. (1) is NOT (2) as frequently as practical D. (1) is NOT (2) after each step is performed Page: 66 of 100 7/5/2017

67. Operators are placing RHR Loop B in Standby. Some MOVs in this loop have black dots on the associated RTGB control switches and are required to be in the closed position.

Which one of the following identifies the proper sequence for valve position verification for these MOV's IAW 2OP-17, Residual Heat Removal System Operating Procedure?

A. An AO must be dispatched to check the valve position locally at the valve using local position indication.

B. The breaker is turned on, the operator checks valve position using red/green indicating lights, then the breaker is turned off.

C. An AO must be dispatched to check the valve position locally by attempting to manually close the valve using the valve hand wheel.

D. The breaker is turned on, the operator strokes the valve open, then closed to ensure proper operation of red/green indicating lights, then the breaker is turned off.

Page: 67 of 100 7/5/2017

68. A reactor startup is in progress on Unit Two IAW 0GP-02, Approach to Criticality and Pressurization of the Reactor.

Reactor power is currently in the Source Range advancing to the POAH Following a notch rod withdrawal of Control Rod 30-31, the Operator at the Controls observes a stable reactor period of 30 seconds.

Which one of the following identifies the required action(s) IAW 0GP-02?

A. Fully insert ALL control rods.

B. Re-insert control rod 30-31 to obtain a stable period between 80 to 180 seconds.

C. Commence rod insertion until at least ten control rods have been fully inserted past the step where the 30 second period was observed.

D. Stop control rod withdrawal and verify period remains stable at 30 seconds or greater. Control rod insertion is NOT required.

Page: 68 of 100 7/5/2017

69. Unit One is in MODE 4 with the following tests being performed IAW 0GP-01, PreStartup Checklist:

Section 6.6, Rod Drift Alarm Test Section 6.7, RMCS Timer Test Which one of the following completes both statements below?

While performing section 6.6, with the Rod Drift Alarm Test Switch in TEST, placing the Emergency Rod In/Rod Override Control Switch to (1) will cause A-05 (3-2)

Rod Drift, (yellow bar) to annunciate.

While performing section 6.7, with a rod selected, placing the RMCS Timer Test Switch in TESTuntil the unit times out (2) result in a select block.

A. (1) EMERG ROD IN (2) will B. (1) EMERG ROD IN (2) will NOT C. (1) OVER RIDE (2) will D. (1) OVER RIDE (2) will NOT Page: 69 of 100 7/5/2017

70. Which one of the following completes both statements below IAW AD-HU-ALL-0004, Procedure and Work Instruction Use and Adherence?

During execution of a procedure a typographical error is noted, a formal procedure revision (1) required prior to completing the procedure.

Supervisor approval (2) required before continuing execution of the procedure.

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: 70 of 100 7/5/2017

71. Unit Two is shutdown with crew performing 0GP-06, Cold Shutdown to Refueling (Head Unbolted).

IAW AD-OP-ALL-0106, Conduct of Infrequently Performed Tests or Evolutions (IPTE),

which one of the following identifies the individual who can fullfill the role of IPTE Manager for the evolution of "Entry into Lowered Inventory" conditions?

A. Shift Manager B. Refuel Floor Supervisor C. Health Physics Supervisor D. Manager Nuclear Maintenance Page: 71 of 100 7/5/2017

72. Which of the following identifies a radiation monitoring system that utilizes an ion chamber detector?

A. Main Stack Radiation Monitoring System B. Liquid Process Radiation Monitoring System C. Main Steam Line Radiation Monitoring System D. Reactor Building Ventilation Exhaust Monitoring System Page: 72 of 100 7/5/2017

73. You have been directed to manually open a valve in the RCA for the performance of a hotspot flush.

The valve is located 6 feet above the RCA floor.

It will initiate flow that will flush a 1 R/hr hotspot through a pipe in an adjacent area.

Radiation levels in the valve area are 15 mR/hour.

The valve area is NOT posted as an Alpha or Airborne Radioactivity Area.

Beta/Gamma contamination levels in the valve area are 2500 dpm/100 cm2.

IAW PD-RP-ALL-0001, Radiation Worker Responsibilities, which one of the following completes the statement below?

Use of the Self-Briefing process is NOT allowed because of the:

A. height of the valve.

B. flushing operation being performed.

C. high radiation levels in the valve area.

D. high contamination levels in the valve area.

Page: 73 of 100 7/5/2017

74. Unit One was operating at 100% power when inadvertent MSIV closure results in RPV pressure peaking at 1131 psig.

Subsequently:

The reactor failed to scram.

The reactor mode switch is in SHUTDOWN.

ARI has been manually initiated.

Reactor power is indicating 4%.

Which one of the following completes both statements below?

(1) Safety Relief Valves have opened automatically.

The operating crew (2) required to trip the recirculation pumps A. (1) Four (2) is B. (1) Four (2) is NOT C. (1) Eight (2) is D. (1) Eight (2) is NOT Page: 74 of 100 7/5/2017

75.

A fire has been confirmed in the Unit Two Cable Spread Room.

Which one of the following completes both statements below?

The Unit Two Cable Spread Room has an installed (1) fire suppression system.

IAW 0PFP-013, General Fire Plan, if the above referenced fire suppression system is not effective in extinguishing the fire, the Fire Brigade (2) permitted to use a firehose to attack the fire.

A. (1) carbon dioxide (2) is B. (1) carbon dioxide (2) is NOT C. (1) water sprinkler (2) is D. (1) water sprinkler (2) is NOT Page: 75 of 100 7/5/2017

76. Which one of the following completes the statement below IAW 0OI-37.4, Reactor Vessel Control Procedure Basis Document?

0EOP-01-SEP-11, Alternative Source Term Actions, is first required if RPV level drops to (1) which is associated with a fuel temperature of (2) .

A. (1) LL4 (2) 1500°F B. (1) LL4 (2) 1800°F C. (1) LL5 (2) 1500°F D. (1) LL5 (2) 1800°F Page: 76 of 100 7/5/2017

77. Unit One is in MODE 4 with the following initial conditions:

RHR Pump A running in the Shutdown Cooling Mode Reactor average temperature 174°F Reactor vessel level 187 inches Current conditions:

A RHR Pump tripped and neither pump in that loop can be restarted.

Reactor pressure is 105 psig.

IAW 0AOP-15.0, Loss of Shutdown Cooling, which one of the following completes both statements below?

A PCIS Group 8 isolation signal (1) occurred.

The CRS will first direct (2) .

A. (1) has (2) a reduction of reactor pressure IAW 0GP-05, Unit Shutdown B. (1) has (2) shifting of shutdown cooling loops IAW 1OP-17, Residual Heat Removal System Operating Procedure C. (1) has NOT (2) a reduction of reactor pressure IAW 0GP-05, Unit Shutdown D. (1) has NOT (2) shifting of shutdown cooling loops IAW 1OP-17, Residual Heat Removal System Operating Procedure Page: 77 of 100 7/5/2017

78. Both units are operating at 100% power with the following conditions on Unit One:

A 61 BTH Dry Shielded Canister (DSC) containing 61 spent fuel assemblies, is inside a Transfer Cask. The dose rate at the top of the Transfer Cask initially on the refuel floor is 2 mR/hr at 30 cm.

This Transfer Cask is then lowered and moved into the Unit One Reactor Building Airlock with both airlock doors closed.

The dose rate at the top of the Transfer Cask is now discovered to be 180 mR/hr at 30 cm. Engineering has determined that a weld has failed due to a manufacturing error that resulted in an inadequate water shield (located between the inner and outer shell of the Transfer Cask).

No emergency declaration was required.

[Reference Provided]

IAW 0OI-01.07, Notifications, which one of the following identifies the latest time that the NRC is required to be notified?

A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Page: 78 of 100 7/5/2017

79. Unit Two was at 100% power when an ATWS occurred with the following plant conditions:

Reactor power 2%

Control Rods Being inserted with RMCS Torus water temperature 109.5°F and rising SLC Pumps A and B both tripped RCIC Injecting from CST Which one of the following completes both statements below?

IAW LEP-03, Alternate Boron Injection, SLC injection will first be attempted using (1) .

In using the system identified above, it will take (2) to achieve hot shutdown boron weight as compared to injection with the SLC System.

A. (1) Section 2.1, CRD SLC Tank Injection (2) shorter B. (1) Section 2.1, CRD SLC Tank Injection (2) longer C. (1) Section 2.2, HPCI/RCIC SLC Tank Injection (2) shorter D. (1) Section 2.2, HPCI/RCIC SLC Tank Injection (2) longer Page: 79 of 100 7/5/2017

80. A small break LOCA occurred on Unit Two.

The following conditions currently exist:

Drywell temperature 270°F Drywell pressure 5.0 psig Torus pressure 2.8 psig Torus level 5 inches Reactor pressure 395 psig Containment Hydrogen Monitors CAC-AT-4409 & 4410 are not available.

Chemistry has been called but has not yet sampled the drywell.

[Reference Provided]

Which one of the following is the procedure that the CRS would direct for these plant conditions?

A. 0EOP-01-SEP-02, Drywell Spray Procedure B. 0EOP-01-SEP-03, Torus Spray Procedure C. 0EOP-01-SEP-05, Primary Containment Purging D. 0EOP-01-SEP-10, Circuit Alteration Procedure (Section 2.1, Defeating Drywell Cooler LOCA Lockout)

Page: 80 of 100 7/5/2017

81. A release is occurring with the following plant conditions:

1-D12-RR-4548-4, TB Vent Effluent Rad Level, is reading 2.195 E+6 µCi/sec 2-D12-RR-4548-4, TB Vent Effluent Rad Level, is reading 1.463 E+4 µCi/sec 2-D12-RR-4548-3-2-1, TB Vent Effluent Rad Level, is reading 4.025 E+0 µCi/cc 2-VA-FT-3358, TB Air Flow, is INOPERABLE 2-VA-FT-7554, TB Total Flow, is reading 7,400 scfm U2 Turbine Building Ventilation System is in recirc mode

[Reference Provided]

Which one of the following identifies the highest emergency action level (EAL) classification that is required for this event?

A. Unusual Event B. Alert C. Site Area Emergency D. General Emergency Page: 81 of 100 7/5/2017

82. Unit One and Unit Two were both operating at 100% power when a large fire in the north section of the Unit Two Reactor Building occurs.

Current Conditions:

Both units remain at 100% power Unit Two CRS determines that entry into the ASSD procedures is required NOTE:

0ASSD-01, Alternative Safe Shutdown Procedure Index 2ASSD-05, Reactor Building North Which one of the following completes both statements below?

Once procedure 0ASSD-01 is entered, the Unit Two CRS is required to (1) .

The Unit Two CRS will enter 2ASSD-05 and (2) 0ASSD-01.

A. (1) always MANUALLY SCRAM Unit Two reactor if power is greater than 2%

(2) exit B. (1) always MANUALLY SCRAM Unit Two reactor if power is greater than 2%

(2) concurrently perform C. (1) make a determination if Unit Two shutdown is required, or not, based on an assessment of the situation (2) exit D. (1) make a determination if Unit Two shutdown is required, or not, based on an assessment of the situation (2) concurrently perform Page: 82 of 100 7/5/2017

83. Unit Two is performing SBO and has just entered Extended Loss of AC Power (ELAP) conditions.

RPV water level is 190 inches and being controlled with RCIC Reactor pressure is 480 psig and being controlled with SRVs Which one of the following completes the statement below?

IAW SBO, the CRS (1) authorized to defeat RCIC automatic logic IAW (2) .

A. (1) is (2) 0EOP-01-SBO-02, BLACKED OUT UNIT INITIAL ACTIONS B. (1) is (2) 0EOP-01-SEP-10, CIRCUIT ALTERATION PROCEDURE C. (1) is NOT (2) 0EOP-01-SBO-02, BLACKED OUT UNIT INITIAL ACTIONS D. (1) is NOT (2) 0EOP-01-SEP-10, CIRCUIT ALTERATION PROCEDURE Page: 83 of 100 7/5/2017

84. Unit Two was in MODE 2 withdrawing rods with SRM D bypassed.

Subsequently, an inadvertant ECCS initiation occurred resulting in off-scale high readings for reactor period on all SRM channels.

After the ECCS initiation was secured, SRM readings are as follows:

Power Period SRM A 710 cps sec SRM B 770 cps sec SRM C 690 cps Off-scale high SRM D 670 cps sec Which one of the following completes both statements below?

The number of currently OPERABLE SRM channels is (1) .

IAW Tech Spec 3.3.1.2 Bases, SRM Instrumentation, a minimum of (2) SRMs are required to be OPERABLE.

A. (1) two (2) two B. (1) two (2) three C. (1) three (2) two D. (1) three (2) three Page: 84 of 100 7/5/2017

85. Following a scram on Unit One, the following conditions currently exist:

Control rods 10 between 04 and 22; all other rods are fully inserted.

Reactor pressure 400 psig and stable Reactor water level 15 inches and stable; High pressure injection ONLY RCIC available and injecting Drywell spray In service on Loop A RHR; Drywell pressure 5 psig and slowly lowering Torus level 6 inches and slowly rising Torus pressure 4 psig and slowly lowering Which one of the following completes both statements below?

0EOP-01-SEP-15, Anticipate Emergency Depressurization, (1) allowed to be entered.

0EOP-01-EDP, Emergency Depressurization, (2) required to be entered.

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: 85 of 100 7/5/2017

86. Unit Two was at 100% power when a transient occurred that caused an auto initiation of HPCI. The following annunciators were received:

A-1 (4-2), HPCI TURB BRG OIL PRESS LO A-1 (1-2), HPCI OIL TANK LEVEL HI/LO The RB AO reports an unisolable oil leak on the HPCI system.

Which one of the following completes both statements below?

If the HPCI oil system completely depressurizes, the final position of 2-E41-V8, HPCI Turbine Stop Valve, will be (1) .

When evaluating Tech Spec 3.5.1, ECCS - Operating, for a subsequent plant startup, use of LCO 3.0.4.b (2) applicable to HPCI.

A. (1) open (2) is B. (1) closed (2) is C. (1) open (2) is NOT D. (1) closed (2) is NOT Page: 86 of 100 7/5/2017

87. For the past three months, Unit Two has been operating at 100% power when main condenser vacuum begins lowering at a steady 2 inches Hg per minute.

Which one of the following completes both statements below?

A reactor scram will first occur as a result of the closure of the (1) .

Assuming a constant rate of lowering vacuum and 15 minutes after the reactor scram, control of RPV pressure will be procedurally maintained IAW (2) .

A. (1) turbine stop valves (2) Reactor Scram Procedure B. (1) main steam isolation valves (2) Reactor Scram Procedure C. (1) turbine stop valves (2) Reactor Vessel Control Procedure D. (1) main steam isolation valves (2) Reactor Vessel Control Procedure Page: 87 of 100 7/5/2017

88. Unit One is operating at 100% power when the following occurs:

A-03 (1-1), SAFETY OR DEPRESS VLV LEAKING, (yellow bar) is in alarm A-03 (1-10), SAFETY/RELIEF VALVE OPEN, (red bar) is in alarm The RO has reported that 1-B21-F013A, Auto Relief A, has a lit amber indication Suppression pool temperature is 95°F and rising slowly Which one of the following completes both statements below?

PCCP actions (1) be performed concurrently with 0AOP-30.0, Safety/Relief Valve Failures, actions.

Upon determination that 1-B21-F013A cannot be closed (fuses were pulled),

the Unit CRS will first direct crew entry into (2) Procedure.

A. (1) will (2) Reactor Vessel Control B. (1) will NOT (2) Reactor Vessel Control C. (1) will (2) Reactor Scram D. (1) will NOT (2) Reactor Scram Page: 88 of 100 7/5/2017

89. Unit Two was at 100% power, when the following timeline occurs:

Time 1300 A Unit Two LOOP occurs Time 1302 E3 and E4 lose power and remain de-energized Time 1325 Power is restored to E8 via FLEX DG2 and E7 remains de-energized Which one of the following completes both statements below?

The CRS will direct de-energization of the Primary UPS IAW (1) .

As required by the SBO Coping Analysis the latest that this action must be completed is by time (2) .

A. (1) 0AOP-36.1, Loss of Any 4160V Buses or 480V E-Buses (2) 1332 B. (1) 0AOP-36.1, Loss of Any 4160V Buses or 480V E-Buses (2) 1402 C. (1) 0EOP-01-SBO-10, Battery Load Stripping (2) 1332 D. (1) 0EOP-01-SBO-10, Battery Load Stripping (2) 1402 Page: 89 of 100 7/5/2017

90. Unit One was operating at 100% power when the following sequence of events occurred:

0900 DG2 running loaded performing 0PT-12-2B, No. 2 Diesel Monthly Load Run 0905 UA-20 (2-1), DG-2 GEN DIFF OVCT TRIP alarms UA-16 (1-1), DG-2 TO BUS E2 BKR TRIP alarms 0910 The CRS is evaluating Tech Spec 3.8.1, AC Sources - Operating, entry criteria. DG1, DG3, DG4, and the Supp DG have been determined to be operable.

Which one of the following completes both statements below?

At 0906, DG2 (1) restart.

Tech Spec 3.8.1 (2) required to be entered.

A. (1) did (2) is B. (1) did (2) is NOT C. (1) did NOT (2) is D. (1) did NOT (2) is NOT Page: 90 of 100 7/5/2017

91. Which one of the following completes both statements below concerning the RWCU system area ventilation high differential temperature Group 3 isolation?

This signal results in a RWCU isolation (1) a 28.5 minute time delay.

For this isolation, if the appropriate valve(s) fail to isolate due to valve failure(s), the CRS will enter Tech Spec 3.6.1.3 Condition(s) (2) .

NOTE:

Tech Spec 3.6.1.3, Primary Containment Isolation Valves (PCIVs)

[Reference Provided]

A. (1) with (2) A ONLY B. (1) with (2) A and B C. (1) without (2) A ONLY D. (1) without (2) A and B Page: 91 of 100 7/5/2017

92. Unit One is operating at 100% power. All rod position information on Panel P603, the Process Computer and ERFIS, has been lost for control rod 02-19. Repairs are NOT expected within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The crew entered 0AOP-02.0, Control Rod Malfunction/Misposition, and are attempting to determine rod position in the RPIS cabinet via reed switch continuity measurements.

The operator determines that continuity exists only between input terminals S and H.

[Reference Provided]

Which one of the following completes both statements below?

IAW 0AOP-02.0, the Equivalent Control Rod Position is (1) .

This determination of control rod position (2) meet the surveillance requirements for Tech Spec 3.1.3, Control Rod Operability.

A. (1) 36 (2) does B. (1) 36 (2) does NOT C. (1) 47 (2) does D. (1) 47 (2) does NOT Page: 92 of 100 7/5/2017

93. Unit One is in MODE 5, with the following conditions:

A-04 (5-7), FUEL POOL GATE RX WELL SEAL in alarm Fuel Pool Gate Seal Pressure is 22 psig and lowering slowly.

NOTE: 0OP-46, Instrument and Service Air System Operating Procedure Which one of the following completes both statements below?

This seal leakage flow is normally directed to (1) .

IAW A-04 (5-7), the Control Room Supervisor will next direct (2) to the Fuel Pool Gate Seals.

A. (1) Radwaste (2) aligning Nitrogen bottles IAW 0OP-46 B. (1) Radwaste (2) aligning the Nitrogen Backup System IAW OP-46 C. (1) the Hotwell (2) aligning Nitrogen bottles IAW 0OP-46 D. (1) the Hotwell (2) aligning the Nitrogen Backup System IAW OP-46 Page: 93 of 100 7/5/2017

94. Unit Two is operating at 60% power with feedwater heaters 4A and 5A bypassed.

A portion of 2OP-32, Condensate and Feedwater System Operating Procedure, Attachment 6, is included below:

[Reference Provided]

Which one of the following completes both statements below IAW 0OI-01.01, BNP Conduct of Operations Supplement?

The Unit CRS is required to implement thermal limit penalties when final feedwater temperature first lowers to less than (1) .

Entry into Tech Spec 3.0.3 (2) required if final feedwater temperature is less than the 110.3°F Reduced FFWT table value.

A. (1) 387.6°F (2) is B. (1) 387.6°F (2) is NOT C. (1) 377.6°F (2) is D. (1) 377.6°F (2) is NOT Page: 94 of 100 7/5/2017

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

IAW 0OI-01.01, BNP Conduct of Operations Supplement, the minimum required number of Auxiliary Operators for manning a shift at BNP is (1) .

IAW Tech Spec 5.2.2, Facility Staff, to accommodate unexpected absences, the total number of non-licensed operators may be less than the minimum requirement for a period of time not to exceed (2) , provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

A. (1) three (2) one hour B. (1) three (2) two hours C. (1) nine (2) one hour D. (1) nine (2) two hours Page: 95 of 100 7/5/2017

96. Which one of the following completes the statements below concerning Temporary Alterations in Support of Maintenance (TAISOMs) IAW 0OI-01.01, BNP Conduct of Operations Supplement?

Disabling an annunciator by pulling the annunciator card in an effort to avoid a nuisance alarm due to (1) , is an example of a TAISOM.

A disabled annunciator controlled as a TAISOM requires a 10CFR 50.59 review if it is expected to be in effect for greater than (2) .

A. (1) testing (2) 14 days B. (1) testing (2) 90 days C. (1) a failed instrument (2) 14 days D. (1) a failed instrument (2) 90 days Page: 96 of 100 7/5/2017

97. Unit Two is at 100% power A BSEP Radioactive Liquid Release Permit is being completed for discharge of the Unit Two Saltwater Release Tank via the General Electric Radiation Monitor IAW 0OP-6.4, Discharging Radioactive Liquid Effluents to the Discharge Canal 2-G16-FIT-N057, Liquid Radwaste Effluent Flow Measurement Device, is INOPERABLE Which one of the following completes both statements below?

IAW the ODCM, the maximum release rate is determined so that (1) limits are not exceeded after dilution in the discharge canal.

IAW 0OP-6.4, release of the Unit Two Saltwater Release Tank (2) .

A. (1) 10 CFR 100, Reactor Site Criteria (2) may be authorized if ODCM compensatory actions are implemented B. (1) 10 CFR 100, Reactor Site Criteria (2) is NOT allowed unless 2-G16-FIT-N057 is OPERABLE C. (1) 10 CFR 20, Standards for Protection Against Radiation (2) may be authorized if ODCM compensatory actions are implemented D. (1) 10 CFR 20, Standards for Protection Against Radiation (2) is NOT allowed unless 2-G16-FIT-N057 is OPERABLE Page: 97 of 100 7/5/2017

98. During accident conditions, an auxiliary operator is needed to enter the reactor building for local emergency actions to save equipment. Due to elevated reactor building radiation levels, it is estimated the operator will receive 12 rem.

IAW 0PEP-3.7.6, Emergency Exposure Controls, which one of the following completes both statements below?

(consider each statement separately)

The (2) is responsible for authorizations of on-site exposures exceeding 10CFR20 limits.

The estimated dose of 12 rem (1) exceed the Emergency Exposure Guidelines for this activity (EPA-400 Limits).

A. (1) Emergency Response Manager (2) will B. (1) Site Emergency Coordinator (2) will C. (1) Emergency Response Manager (2) will NOT D. (1) Site Emergency Coordinator (2) will NOT Page: 98 of 100 7/5/2017

99. Unit One reactor steam dome pressure spikes to 1350 psig and the reactor scrams.

[Reference Provided]

Which one of the following completes the statement below?

IAW 0OI-01.07, Notifications, Attachment 1, Reportability Evaluation Checklist, a reportable event has occurred due to Item #:

A. 1.1 B. 2.3 C. 3.1 D. 3.2 Page: 99 of 100 7/5/2017

100. Following an earthquake, the Unit Two RB AO has reported a lowering level in the spent fuel pool.

Which one of the following completes both statements below IAW SCCP?

The Unit Two CRS will direct the AO to perform (1) to stage the fire water spent fuel pool spray equipment.

IAW the SF/L leg, spray the spent fuel pool before spent fuel pool level drops to a minimum of (2) .

A. (1) 0EOP-01-SEP-12, Fuel Pool Level Control (2) 17 feet 3 inches B. (1) 0EOP-01-SEP-12, Fuel Pool Level Control (2) 19 feet 11 inches C. (1) 0EDMG-002, Portable Sprays and Enhanced Ventilation Under Conditions of Extreme Damage (2) 17 feet 3 inches D. (1) 0EDMG-002, Portable Sprays and Enhanced Ventilation Under Conditions of Extreme Damage (2) 19 feet 11 inches Page: 100 of 100 7/5/2017

2017 NRC Written Exam Answer Key BRUNSWICK Name: _ _ _ _ __

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