ML15300A490

Inital Exam 2015-301 Final RO Written Exam

ML15300A490
Person / Time
Site:	Vogtle
Issue date:	10/27/2015
From:	Division of Nuclear Materials Safety II
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Download: ML15300A490 (78)

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ANSWER KEY REPORT for Test Test Form: 0 Answers

1. ID Points Type 0 1 002K6.03 1 1.00 MCS A 2 003K5.02 1 1.00 MCS D 3 003K6.04 1 1.00 MCS D 4 004K2.06 1 1.00 MCS B 5 004K5.30 1 1.00 MCS B 6 005K2.01 1 1.00 MCS B 7 006A3.03 1 1.00 MCS B 8 007A3.01 1 1.00 MCS A 9 OO7EK1.05 1 1.00 MCS B 10 OO8AA1.03 1 1.00 MCS D 11 008G2.4.4 1 1.00 MCS A 12 008K1.01 1 1.00 MCS A 13 OO9EA1,06 1 1.00 MCS A 14 010K4.021 1.00 MCS A 15 O11EK3.01 1 1.00 MCS C 16 011K2.021 1.00 MCS D 17 012A1,01 1 1.00 MCS B 18 012K6.03 1 1.00 MCS A 19 013A1.041 1.00 MCS C 20 013A4.02 1 1.00 MCS C 21 015AA2.11 1 1.00 MCS C 22 015K5.09 1 1.00 MCS A 23 016A4.01 1 1.00 MCS B 24 022A1.04 1 1.00 MCS A 25 022AK1.03 1 1.00 MCS D 26 024AA1.23 1 1.00 MCS D 27 025AK2.02 1 1.00 MCS A 28 026A4.05 1 1.00 MCS A 29 026AG2.4.46 1 1.00 MCS B 30 029EA2.05 1 1.00 MCS B 31 033A3.02 1 1.00 MCS D 32 034K1.04 1 1.00 MCS A 33 035K3.01 1 1.00 MCS B 34 036AK3.03 1 1.00 MCS B 35 038EK1.02 1 1.00 MCS B 36 039A2.04 1 1.00 MCS A 37 039K5.08 1 1.00 MCS D 38 054AK3.04 1 1.00 MCS A 39 056AA2.20 1 1.00 MCS D 40 057AG2.4.35 1 1.00 MCS D 41 059AG2.1.23 1 1.00 MCS A 42 059G2.4,11 1 1.00 MCS B 43 061K6.01 1 1.00 MCS C 44 062AK3.01 1 1.00 MCS D 45 062K1.04 1 1.00 MCS C 46 063K1.03 1 1.00 MCS B Monday, September 28, 2015 10:33:23AM

{cH JL ct-/5 ANSWER KEY REPORT for Test Test Form: 0 Answers

1. ID Points Type 0 47 064A4.01 1 1.00 MCS D 48 065AA1.04 1 1.00 MCS D 49 071A1,061 1.00 MCS D 50 073A2.02 1 1.00 MCS A 51 074EA1.17 1 1.00 MCS B 52 076K3.01 1 1.00 MCS C 53 078K4.03 I 1.00 MCS D 54 079K4.01 1 1.00 MCS B 55 086G2.2.22 1 1.00 MCS B 56 103A2.05 1 1.00 MCS B 57 103K3.03 1 1.00 MCS A 58 G2.1.15 1 1.00 MCS C 59 G2.1.17 1 1.00 MCS C 60 G2.1.27 1 1.00 MCS B 61 G2.2.42 1 1.00 MCS C 62 G2.2.44 1 1.00 MCS C 63 G2.3.11 1 1.00 MCS C 64 G2.3.12 1 1.00 MCS A 65 G2.4.1 1 1.00 MCS C 66 G2.4.14 1 1.00 MCS C 67 G2.4.37 1 1.00 MCS C 68 WEO1EK2.01 1 1.00 MCS C 69 WEO3EA2.02 1 1.00 MCS D 70 WEO4EK2.01 1 1.00 MCS C 71 WEO5EK2.02 I 1.00 MCS D 72 WE12EG2.4.20 1 1.00 MCS B 73 WE13EK3.04 1 1.00 MCS A 74 WE14EK1.02 1 1.00 MCS B 75 WE16EA2.02 1 1.00 MCS D SECTION 1 (75 items) 75.00 Monday, September 28, 2015 10:33:23 AM 2

HL2O NRC RO Exam Provided References Index

1. EOP 19030-C Step 50 Control RCS Pressure and Charging

2. AOP 18016-C Attachment 1 Turbine Load Restrictions based on Steam Flow

1.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- 1 NAA de-energized due to a fault.

Current conditions:

- 19200-C, Critical Safety Function Status Trees, is initiated.

- RCS pressure is 1800 psig and stable.

- All RCP 1 E breaker handswitch red lights are lit.

- RCPs #2 and #4 non-i E breaker handswitch red lights are lit.

- RCPs #1 and #3 non-i E breaker handswitch green lights are lit.

Which one of the following completes the following statement?

The RVLIS dynamic range level indication _(i )_ providing accurate input to the Core Cooling status tree, and the RVLIS level indication (2) density compensated.

_(1 )_ _(2)_

A. is is B. is is NOT C. is NOT is D. is NOT is NOT

2.

Initial conditions:

- Unit 1 is at 20% reactor power following an outage.

- 12004-C, Power Operation (Mode 1), is in progress.

Current conditions:

- An automatic reactor trip occurred due to a grid disturbance.

- 19001-C, Reactor Trip Response, is in progress.

- All RCP 1 E breakers are open.

- All RCP non-1 E breakers are closed.

Which one of the following completes the following statement?

The reactor automatically tripped due to (1),

and per the bases of Tech Spec LCO 3.3.1, RTS Instrumentation, this automatic reactor trip ensures (2).

A. (1) RCS two loop low flow (2) the RCPs are protected from excessive current B. (1) RCS two loop low flow (2) sufficient RCP coastdown time to avoid violating DNBR C. (1) RCP underirequency (2) the RCPs are protected from excessive current D. (1) RCP underfrequency (2) sufficient RCP coastdown time to avoid violating DNBR

3.

Initial conditions:

- Unit 2 is at 100% reactor power.

- 2BY1 B is de-energized due to a fault.

Current condition:

- Unit 2 reactor trip and SI occur due to a LOCA.

Which one of the following completes the following statement?

ACCW flow to the RCP thermal barrier _(1) isolated, and RCP seal return flow is currently being directed to the _(2)_.

(1 )

A. is VCT B. is PRT C. is NOT VCT D. is NOT PRT

4.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Letdown flow is 120 gpm.

- Pressurizer level control is selected to CH 459 / 460.

Current conditions:

- One 120 VAC vital bus de-energized.

- Letdown flow remains at 120 gpm.

Which one of the following identifies the specific 120 VAC vital bus that de-energized?

A. 1AY1A B. 1AY2A C. 1BY1B D. 1BY2B

5.

Initial conditions:

- Unit 1 is in Mode 5 on solid plant pressure control.

- RHR Train A is in service for temperature control.

- RHR letdown is in service.

- 1 FIC-1 21, Charging Line Control, is in manual.

- 1PIC-131, LP Letdown Control, is in manual.

Current condition:

- CCW Train A pumps trip on low surge tank level.

Which one of the following completes the following statement?

Over the next 10 minutes with no operator action, letdown flow rate will _(1 )_,

and charging flow rate will (2).

(1)

A. rise rise B. rise lower C. lower rise D. lower lower

6.

Initial conditions:

- Unit 2 is in Mode 4.

- RHR Train A is aligned for ECCS injection.

- RHR Train B is in service for temperature control.

- 2BA03 is energized by the SAT.

Current conditions:

- Both RATs de-energize due to a lightning strike.

- Plant Wilson is NOT affected.

Which one of the following completes the following statement?

The 4160 VAC bus breaker supplying RHR pump A is _(1)_,

and the 4160 VAC bus breaker supplying RHR pump B is (2).

(1 ).

A. open open B. open closed C. closed open D. closed closed

7.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- Unit 1 reactor trip and SI occurs.

Which one of the following completes the following statement?

The white indicating lights on handswitches 1 HS-8508A and B, CCP RV to RWST Isolation, _(1)_ lit, and their associated valves, 1 HV-8508A and B, will operate automatically in response to input from a(an) _(2)_ pressure transmitter signal.

_(1 )_ _(2).

A. are RCSWR B. are CCP discharge C. are NOT RCSWR D. are NOT CCP discharge

8.

Initial conditions:

- Unit2isin Mode 5.

- RHR Train A is in service for shutdown cooling.

Current condition:

- ALB12-E02 PRZR REL TANK HI PRESS is received.

Which one of the following completes the following statement?

The RHR pump A (1) relief valve lifting will cause the PRT high pressure condition, and with no operator action, 2P1-469, PRT Pressure, on the QMCB will reach a maximum of (2) psig before the rupture disk fails.

(1 )

A. suction 100

8. suction 1 15 C. discharge 100 D. discharge 115

9.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- Unit 1 reactortrips.

- Steam dumps are NOT available.

- RCS Tavg is stable and controlled by the ARVs in automatic.

Which one of the following completes the following statement?

Over the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, with no operator action, ARV controller demand output will A. rise B. lower C. remain the same D. rise and then lower

10.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a pressurizer steam space leak.

- 1901 2-C, Post-LOCA Cooldown and Depressurization, was entered.

Current conditions:

- Crew is at the step to Initiate RCS cooldown to cold shutdown.

- Steam dumps are in the Steam Pressure Mode.

Which one of the following completes the following statement?

Per 19012-C, the RCS cooldown rate will be monitored using RCS _(1)_ leg temperatures, and per 19012-C, the cooldown is initiated by (2) demand on 1 PIC-507, Steam Dump Control.

_(1 )_ _(2)_

A. hot lowering B. hot raising C. cold lowering D. cold raising

11.

Initial conditions:

- Unit 1 is at 100% reactor power.

- CCW Train A is in service.

- ALB36-A01 4160V SWGR 1AA02 TROUBLE is received and does NOT clear.

- Multiple CCW Train A low pressure and low flow alarms are received, then clear.

Current condition:

- CCW Train A pressure and flow are normal and stable.

Which one of the following completes the following statement?

One CCW Train A pump has experienced a (1),

and entry into 18020-C, Loss of Component Cooling Water, _(2)_ required.

_(1 )_

A. locked rotor is B. locked rotor is NOT C. sheared shaft is D. sheared shaft is NOT

12.

Initial conditions:

- Unit 2 is at 100% reactor power.

- ACCW pump #2 is in service.

- ACCW pump #1 is in standby.

Current conditions:

- NSCW Train B is shut down due to a piping break.

- No other operator action has been taken.

Which one of the following completes the following statement?

Cooling _(1)_ being provided to the ACCW pump #2 motor, and cooling (2)_ being provided to the ACCW system loads.

_(1 )_

A. is is B. is is NOT C. is NOT is D. is NOT is NOT

13.

Given the following:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- 19010-C, Loss of Reactor or Secondary Coolant, is in progress.

- OATC is assigned to monitor CSFSTs per 19200-C, Critical Safety Function Status Trees.

Which one of the following completes the following statement?

To ensure the CSFSTs are indicating correctly for the given plant conditions, the OATC is required to verify the IPC indicates Mode (1),

and on the IPC, an active CSFST RED path is depicted by a _(2)_ line.

(1 )

A. 0 solid B. 0 hollow C. 3 solid D. 3 hollow

14.

Initial conditions:

- Unit 1 is at 25% reactor power.

- All pressurizer backup heaters are in automatic.

- Variable pressurizer heaters are in the ON position.

- Due to a pressurizer level control malfunction, pressurizer level lowers to 15%

and pressurizer pressure lowers to 2180 psig.

Current conditions:

- Pressurizer level is 25% and slowly rising.

- Pressurizer pressure has returned to 2215 psig.

Which one of the following completes the following statement?

Assuming no operator action, the pressurizer variable heaters are (1 )_,

and the pressurizer backup heaters are _(2)_.

_(1 )_ _(2)_

A. off off B. oft on C. on off D. on on

15.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a large break LOCA.

Current conditions:

- 19000-C, Reactor Trip or Safety Injection, UO Initial Actions are in progress.

- Containment pressure is 22.5 psig.

Which one of the following completes the following statement?

For the given conditions, the main steam lines are verified isolated to (1 )_,

and handswitch 1 HS-3007A, SLI Actuation, (2) send an actuation signal to the Train B MSIVs and Train B BSIVs.

A. (1) prevent a return to criticality (2) will B. (1) prevent a return to criticality (2) will NOT C. (1) distinguish between a primary and secondary break (2) will D. (1) distinguish between a primary and secondary break (2) will NOT

16.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Loss of off-site power to 1AAO2 and 1 BAO3 occurs.

Current conditions:

- DG1 B starts, re-energizes its associated bus, and completes the loading sequence.

- DO1A will NOT start.

Which one of the following completes the following statements?

The power supplies to the Tech Spec pressurizer heater groups are (1 ).

Based on the current conditions, Tech Spec LCO 3.4.9, Pressurizer, _(2)_ met.

(1 )_ (2)

A. 1 NBO8 and 1 NBO9 is B. 1 NBO8 and 1 NBO9 is NOT C. 1NBO1 and 1NB1O is D. 1NBO1 and 1NB1O is NOT

17.

Initial condition:

- Unit 2 is at 70% reactor power.

Current conditions:

- Pressurizer pressure control malfunction causes pressurizer pressure to rise.

- RCS Tavg is constant.

Which one of the following completes the following statement?

Based on the given conditions, the CT delta T reactor trip setpoint will _(1 )_,

and the OP delta T reactor trip setpoint will (2).

_(1 )_

A. rise rise B. rise not change C. lower rise D. lower not change

18.

Initial conditions:

- Unit 1 is at 100% reactor power.

- 1 PT-456, Pressurizer Pressure, fails off-scale high.

Current condition:

- All bistables associated with 1 PT-456 have been placed in their Tech Spec required state.

Which one of the following completes the following statement?

The minimum number of additional Pressurizer Pressure channels failing high required to initiate a reactor trip is (1 ),

and the minimum number of additional Pressurizer Pressure channels failing low required to initiate a safety injection is (2)_.

(1 )

A. 1 1 B. 1 2 C. 2 1 D. 2 2

19.

Initial conditions:

- Unit 1 reactor tripped from 35% reactor power.

- MFP A is running.

Current conditions:

- 19001-C, Reactor Trip Response, is in progress.

- Crew is at Step 4 to Limit RCS Cooldown.

- SG NR levels are 33% in each SG.

- MDAFW flow is throttled to 50 gpm to each SG.

Which one of the following completes the following statement?

Based on the current conditions, when the UO trips MFP A, the MDAFW pump discharge valves will (1),

and the MDAFW pump discharge valves handswitch white lights (2)_ be lit.

(1 ). _(2).

A. re-open fully will B. re-open fully will NOT C. remain throttled will D. remain throttled will NOT

20.

Initial condition:

- Unit 2 reactor trip and SI occurred due to a LOCA.

Current conditions:

- Reactor Trip Breaker B will NOT open.

- RCS pressure is 22 psig.

Which one of the following completes the following statement?

The Train B SI signal (1) be reset, and the Train B CVI signal _(2)_ be reset.

_(1 )_ _(2)_

A. can can B. can can NOT C. can NOT can D. can NOT can NOT

21.

Initial conditions:

- Unit 1 reactor is tripped due to a total loss of ACCW.

- All RCPs are stopped.

- 19221-C, Response to Inadequate Core Cooling, is in progress.

Current conditions:

- SGs are depressurized to less than 200 psig.

- CETCs are 1220°F and rising.

- SG #1 NR level is 40%.

- The crew is at the step to Check if an idle RCS cooling loop is available.

Which one of the following completes the following statement?

Based on the given conditions, normal RCP support conditions (1 ) required prior to starting an available RCP, and 19221-C requires a minimum SC NR level in an idle RCS loop prior to starting an RCP to minimize the risk of _(2)_.

_(1 )_ _(2).

A. are creep rupturefailure B. are pressurized thermal shock C. are NOT creep rupture failure D. are NOT pressurized thermal shock

22.

Initial conditions:

- Unit 1 is at 90% reactor power.

- All control systems are in automatic.

- Power Range N41 fails high.

Current condition:

- 18002-C, Nuclear Instrumentation System Malfunction, is entered.

Which one of the following completes the following statements?

Based on the given conditions, automatic rod motion (1 ) occur.

Per 18002-C, the Movable Incore Detector System _(2)_ used to confirm QPTR.

_(1 )_ _(2)_

A. did is B. did is NOT C. did NOT is D. did NOT is NOT

23.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- One Loop 1 NR temperature instrument fails low.

Which one of the following completes the following statement?

To remove the Loop 1 Tavg input to the rod control system, the operator is required to and completing this action _(2)_ remove the Loop 1 Tavg input to the Low Tavg Feedwater Isolation (FWI) circuit.

A. (1) place 1 TS-41 2T, Tavg Defeat Sel switch, to the affected loop (2) will B. (1) place 1TS-412T, Tavg Defeat Sel switch, to the affected loop (2) will NOT C. (1) trip the associated temperature instruments bistables (2) will D. (1) trip the associated temperature instruments bistables (2) will NOT

24.

Initial conditions:

- Unit 1 reactor tripped due to an inadvertent SI.

- All equipment automatically aligned as required.

Current conditions:

- SI has been reset.

- NSCW Train A header pressure is lowering.

- NSCW Train A return header flow is lowering.

- Containment sump levels are rising.

Which one of the following completes the following statement?

Based on the given conditions, a rupture has occurred in the cooling coils of a (1 ) Cooling Unit, and NSCW flow to the leaking Cooling Unit _(2) be isolated from the QMCB.

(1)

A. Containment can B. Containment can NOT C. Reactor Cavity can D. Reactor Cavity can NOT

25.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- The following alarms are received:

- ALBO7-A05 REGEN HX LTDN HI TEMP

- ALBO7-B06 CHARGING LINE HI / LO FLOW

- ALBO7-D03 LTDN HX OUT HI TEMP

- ALBO8-F06 RCP SEAL WATER INJ LO FLOW

- No operator action has been taken.

Which one of the following completes the following statement?

Based on the given conditions, (1) has failed closed, and pressurizer level is _(2)_.

_(1 )

A. 1 HV-1 82, Seal Flow Control rising B. 1 HV-1 82, Seal Flow Control lowering C. 1 FV-121, Charging Flow Control rising D. 1 FV-1 21, Charging Flow Control lowering

26.

Initial conditions:

- Unit 2 is at 70% reactor power.

- Control rods are stepping out without demand.

- Reactor will NOT trip from the QMCB.

- 1921 1 -C, Response to Nuclear Power Generation / ATWT, is entered.

- Boric Acid Transfer Pump (BATP) A is started to establish emergency boration.

Current condition:

- BATP A trips.

Which one of the following completes the following statement?

BATP B _(1 )_ automatically start when BATP A trips, and per 19211-C, the minimum charging flow is required to be greater than (2) gpm as indicated on 2Fl-121, Charging Flow.

(1 ) _(2)_

A. will 30 B. will 42 C. will NOT 30 D. will NOT 42

27.

Initial conditions:

- Unit 1 is in Mode 5.

- RHR pump A is in service for shutdown cooling.

Current conditions:

- RCS level is 187 feet and lowering due to a leak.

- RCS temperature is 190 °F.

- 18019-C, Loss of Residual Heat Removal, is in progress.

Which one of the following completes the following statements?

Per 18019-C, the operating crew(1) required to stop RHR pump A.

Per 18019-C, if no pump is available, the preferred gravity drain path to restore inventory is through the (2) pumps to the RCS cold legs.

_(1 )_

A. is RHR B. is SI C. is NOT RHR D. is NOT SI

28.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- OATC manually actuated Containment Spray (CS) from the QMCB C panel.

Current condition:

- Containment pressure is 23.8 psi.

9 Which one of the following completes the following statement?

To manually actuate CS, the OATC 1) required to simultaneously operate both CS Actuation handswitches, 1 HS-4001 0 and 1 HS-4001 1, on the C panel, and based on the current condition, if the OATC takes both the CS Reset handswitches to the RESET position, the CS actuation signal _(2)_ reset.

_(1 )_ _(2).

A. was will B. was will NOT C. was NOT will D. was NOT will NOT

29.

Initial conditions:

- Unit 1 is at 100% reactor power.

- CCW pumps #1 and #3 are running.

Current conditions:

- ALBO2-A05 COW TRAIN A SURGE TK LO-LO LVL is received.

- CCW pump #3 trips.

- CCW pump #lis running.

- The following alarms are received:

- ALBO2-A06 CCW TRAIN A LO HDR PRESS

- ALBO2-B06 CCW TRAIN A LO FLOW

- ALBO2-D06 COW TRAIN A RHR HX LO FLOW

- ALBO2-E05 CCW TRAIN A RHR PMP SEAL LO FLOW Which one of the following completes the following statement?

COW pump #3 (1) trip due to a COW Train A Surge Tank level transmitter tailing low, and the standby COW pump will automatically start due to low CCW header (2).

_(1 ).. _(2)_

A. did flow B. did pressure C. did NOT flow D. did NOT pressure

30.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Containment mini-purge is in service for pressure relief.

Current conditions:

- Unit 1 experiences an ATWT.

- 1921 1-C, Response to Nuclear Power Generation / ATWT, is in progress.

- Crew is at the step to Check Containment Ventilation Isolation.

- Train A CVI MLBs are lit.

- Train B CVI MLB5 are NOT lit.

Which one of the following completes the following statement?

Based on the current conditions, the mini-purge flow path from containment (1) isolated, and per 19211-C, the Train _(2)_ CVI dampers and valves are required to be closed manually.

(1) (2)

A. is A B. is B C. is NOT A D. is NOT B

31.

Initial conditions:

- A fuel shuffle is in progress on Unit 2.

- All SEP cooling pumps are in service.

Current condition:

- Unit 2, SEP cooling pump A seal fails.

Which one of the following completes the following statement?

With no operator action, SEP inventory loss will stop due to uncovering the _(1)_,

and SEP water level _(2)_ remain above the minimum required by Tech Spec LCO 3.7.15, Euel Storage Pool Water Level.

(1 )

A. siphon breaker will B. siphon breaker will NOT C. pump suction piping will D. pump suction piping will NOT

32.

Initial conditions:

- Unit us in Mode 6 for a refueling outage.

- Control rod latching and verification is in progress.

- Source Range N31 is providing audible indication.

Current condition:

- Source Range N32 fails low.

Which one of the following completes the following statements?

TR 13.9.6, Source Range Monitor Audible Indication, (1) met.

t Based on the given conditions, core alterations are required to be suspended _(2)_.

_(1 )_

A. is immediately B. is in no later than 15 minutes C. is NOT immediately D. is NOT in no later than 15 minutes

33.

Initial conditions:

- Unit 1 is in Mode 3.

- A steam leak is reported in the Turbine Building.

Current condition:

- The UO actuates SLI.

Which one of the following completes the following statement?

A steam line break has the greatest reactivity impact on the reactor at the (1 ) of core life, and assuming no additional operator action, RCS temperature will stabilize at approximately (2)_ °F.

_(1 )_ _(2)_

A. end 557 B. end 561 C. beginning 557 D. beginning 561

34.

Initial condition:

- Fuel shuffle is in progress in the Unit 2 SEP.

Current conditions:

- An irradiated fuel assembly is dropped.

- ARE-2532A and B are in high alarm.

- 18006-C, Fuel Handling Event, is entered.

Which one of the following completes the following statement?

Per 18006-C, to ensure proper FHB HVAC alignment, the UO is required to (1) one FHB Post-Accident Exhaust unit, and establishing this required alignment is done to limit the _(2).

(1 ) _(2)..

A. stop airborne concentrations in the FHB B. stop off-site release C. start airborne concentrations in the FHB D. start off-site release

35.

Initial conditions:

- Unit 2 reactor trips due to a 175 gpm SGTR on SG #1.

- RCS pressure is 2100 psig.

- SG #1 pressure is 990 psig.

- 1 9030-C, Steam Generator Tube Rupture, is entered.

Current conditions:

- RCS pressure is 1260 psig.

- SG #1 pressure is 1120 psig.

- SG #1 NR level is 81% and slowly rising.

- Pressurizer level is 76%.

- Containment pressure is 0.1 psig.

- Crew is at the step to Control RCS pressure and charging flow to minimize RCS-to-secondary leakage.

Which one of the following completes the following statement?

The current SG leak rate is approximately (1 ) gpm, and based on the current conditions, the OATC _(2)_ required to continue depressurization of the RCS to control primary to secondary leakage.

REFERENCES PROVIDED A. 80 is B. 80 is NOT C. 135 is D. 135 is NOT

36.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- 1 PT-506, Turbine Power, fails low.

Which one of the following completes the following statement?

The QMCB B panel STEAM DUMP ARMED light on ZLB-2 _(1)_ be lit, and per 18001-C, Systems Instrumentation Malfunction, the steam dumps (2) required to be placed in the Steam Pressure Mode.

(1)

A. will are B. will are NOT C. will NOT are D. will NOT are NOT

37.

Initial conditions:

- Unit 1 experienced an ATWT at EOL conditions.

- 1921 1 -C, Response to Nuclear Power Generation / ATWT, is in progress.

Current conditions:

- Emergency Boration can NOT be established.

- Crew is at Step 23 to Check reactor power.

- Reactor power is 8%.

- IR SUR is negative.

- RCS temperature is 563 °F and slowly rising.

- RCS pressure is 2285 psig.

Which one of the following completes the following statement?

Based on the given conditions, per 19211-C, the crew (1) required to dump steam to lower RCS temperature, and per 19211-C, the RCPs (2) required to be stopped.

_(1 )_ _(2)_

A. is are B. is are NOT C. is NOT are D. is NOT are NOT

38.

Initial conditions:

- Unit 1 reactor tripped due to a loss of feedwater.

- Reactor Trip Breaker A is NOT open.

- Reactor Trip Breaker B is open.

Current conditions:

- 19231-C, Response to Loss of Secondary Heat Sink, is in progress.

- RCS bleed and feed is in progress.

- The crew is re-establishing feedwater using a MFP.

Which one of the following completes the following statement?

The Bypass Feedwater Isolation Valves (BFIV5) were closed (1),

and to re-establish feedwater flow, the Reactor Trip Breakers are cycled to allow the

_(2) signal to be reset.

A. (1) automatically due to the Feedwater Isolation (FWI) signal (2) FWI B. (1) automatically due to the Feedwater Isolation (FWI) signal (2) SI C. (1) manually by the UO when verifying FW isolation valves closed (2) FWI D. (1) manually by the UO when verifying FW isolation valves closed (2) SI

39.

Initial conditions:

- Unit 1 is at 100% reactor power.

- RAT lA de-energizes due to a fault.

- DG1A starts and re-energizes its associated bus.

- Load sequencing is complete.

Current conditions:

- 18031-C, Loss of Class 1 E Electrical Systems, is entered.

- Unit 1 reactor power is 100.8%.

- AFW flow indications are as follows:

- SG#1 is4o8gpm.

- SC #2 is4logpm.

- SC #3 is4o5gpm.

- SG#4is4o6gpm.

- No operator action has been taken.

Which one of the following completes the following statement?

To lower TDAFW pump flow, the UO will use the (1 ) control mode on controller 1 PDIC-51 80A, TDAFW Cntl Delta P-Feed to Stm, and the MDAFW pumps _(2)_ operating as expected for the given conditions.

(1 ). _(2)_

A. delta-P are B. delta-P are NOT C. speed are D. speed are NOT

40.

Initial conditions:

- Unit 1 is at 100% reactor power.

- 1 BY2B is de-energized.

Current condition:

- Systems Operator transferred 1 BY2B to its alternate power source.

Which one of the following completes the following statements?

The alternate power source for 1 BY2B is a(n) (1).

If off-site power is lost, based on the current conditions the Train B sequencer (2)_

start DG1B.

(1 ) _(2)_

A. inverter will B. inverter will NOT C. regulated transformer will D. regulated transformer will NOT

41.

Initial conditions:

- Unit 1 is in a refueling outage.

- Turbine building drains are being pumped down.

Current condition:

- 1 RE-0848, Turbine Building Drains, is in high alarm.

Which one of the following completes the following statement?

The turbine building normal drain flow path (1)_ automatically isolate, and per 17100-1, Annunciator Response Procedure for the Process and Effluent Radiation Monitoring System (RMS), the Systems Operator is required to verify that the turbine building drains are aligned to the _(2).

_(1 )

A. will Dirty Drain Tank B. will Waste Water Retention Basin C. will NOT Dirty Drain Tank D. will NOT Waste Water Retention Basin

42.

Initial conditions:

- Unit 2 is at 100% reactor power.

- Feedwater heaters 4A and 5A extraction steam valves fail closed due to a common mode failure.

Current conditions:

- 18016-C, Condensate and Feedwater Malfunction, is in progress.

- Operators reduced turbine load and power is stable at 100% RTP.

Which one of the following completes the following statement?

During the initial loss of feedwater heaters, the PR Nis will indicate (1) than actual reactor power, and per 18016-C, the operators (2) required to commence additional turbine load reduction.

REFERENCES PROVIDED (1 )

A. lower are B. lower are NOT C. higher are D. higher are NOT

43.

Initial conditions:

- Unit 1 experienced a loss of heat sink.

- TDAFW pump governor developed a hydraulic oil leak.

- TDAFW pump tripped on overspeed.

- 1 HS-1 5111, TDAFW Trip and Throttle Valve, green and amber lights are lit.

Current condition:

- OAO is dispatched to reset the TDAFW pump mechanical overspeed trip.

Which one of the following completes the following statement?

The amber light on 1HS-15111 will extinguish when _(1)_,

and with the failed governor valve, the TDAFW pump (2) be operated locally.

A. (1) 1 HS-51 06A, TDAFW Steam Supply, is taken to the close position (2) can B. (1) 1 HS-51 06A, TDAFW Steam Supply, is taken to the close position (2) can NOT C. (1) the mechanical trip linkage is manually reset (2) can D. (1) the mechanical trip linkage is manually reset (2) can NOT

44.

Initial conditions:

- Unit 1 is at 100% reactor power.

- NSCW Train A was shutdown due to the loss of pumps #3 and #5.

Current conditions:

- NSCW pump #3 has been repaired.

- NSCW pumps #1 and #3 are being started simultaneously from standby.

Which one of the following completes the following statement?

NSCW Train A discharge header is repressurized by _(1)_,

and this method of repressurization is designed to limit _(2)_.

(1 )

A. its discharge valve throttling DG1A current B. its discharge valve throttling water hammer C. flow through a bypass line DG1A current D. flow through a bypass line water hammer

45.

Initial conditions:

- Unit 1 is operating at 60% reactor power with a plant startup in progress.

- ACCW pump #1 is in service.

Current conditions:

- Both Unit 1 RATs de-energize.

- Both DGs start and re-energize their respective buses.

- No other switchyard components are affected.

Which one of the following completes the following statement?

With no operator action, one minute after the RATs de-energize, the Reactor Trip Breakers will be (1),

and per 18031-C, Loss of Class 1 E Electrical Systems, the crew is required to (2) one ACCW pump.

(1 )

A. open stop B. open start C. closed stop D. closed start

46.

Initial conditions:

- Unit 1 is at 100% reactor power.

- A loss of off-site power occurs.

Current conditions:

- DG1A starts and re-energizes its associated bus.

- DG1 B will NOT start.

- 1 BD1 bus voltage is 103 VDC.

Which one of the following completes the following statements?

Two battery chargers in service on 1 BD1 _(1) the normal operational alignment.

Based on the given conditions, per 18031-C, Loss of Class 1 E Electrical Systems, the minimum required action is to 2).

A. (1) is (2) open its associated battery breaker B. (1) is (2) shutdown its associated inverter and then open its battery breaker C. (1) is NOT (2) open its associated battery breaker D. (1) is NOT (2) shutdown its associated inverter and then open its battery breaker

47.

Given the following:

- Unit 1 is at 100% reactor power.

- DG1A is paralleled to the grid and loaded to 7000 kW.

Which one of the following completes the following statement?

Based on the given conditions, DG1A (1) operating in the UNIT mode, and to directly change the kVAR / reactive loading of DG1A, the UO is required to depress the 2)_ CONTROL pushbuttons on the QEAB.

(1 ).. _(2)_

A. is SPEED B. is VOLTAGE C. is NOT SPEED D. is NOT VOLTAGE

48.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- 1 P1-9377, Service Air Header Pressure, is 92 psig and slowly lowering.

- 18028-C, Loss of Instrument Air, is in progress.

Which one of the following completes the following statement?

Based on the given conditions, 1 PV-9375, Service Air Dryer Inlet Isolation Valve, (1) closed, and per 18028-C, a Systems Operator will be dispatched to manually align a back-up

_(2)_ to supply the River Intake Air System.

.(1 ).

A. is nitrogen bottle B. is air compressor C. is NOT nitrogen bottle D. is NOT air compressor

49.

Initial conditions:

- Unit 1 transfer of Gas Decay Tank #2 contents to Gas Decay Tank #4 is in progress.

- Auxiliary Building Supply and Exhaust HVAC is in service.

Current conditions:

- 1 RE-0039A, Waste Gas Decay Tank Radiogas, is in high alarm.

- 1 RE-0039B, Waste Gas Compressor Radiogas, is in high alarm.

- 1 RE-12442C, Plant Vent Radiogas Particulate (Low Range), is in high alarm.

Which one of the following completes the following statement?

Per 17100-C, Annunciator Response Procedure for the Process and Effluent Radiation Monitoring System (RMS), the operators are required to (2).

A. manually start the Piping Penetration Units B. manually secure all Auxiliary Building HVAC C. manually secure only the Auxiliary Building Normal Supply Units D. continue monitoring radiation levels, but no additional action associated with Auxiliary Building HVAC is required

50.

Valve names as follows:

- 1 FV-1 150, Blowdown In let Isolation Valve

- 1 HV-7600, Blowdown Recycle Isolation Valve Initial condition:

- Unit 1 is at 100% reactor power.

Currrent condition:

- 1 RE-0021, SG Blowdown Liquid, fails high.

Which one of the following completes the following statement?

Unit 1 thermal power, as indicated by UQ-1 118, (1) be affected by the failure, and per 17100-1, Annunciator Response Procedure for the Process and Effluent Radiation Monitoring System (RMS), the operators will verify that blowdown isolation valve (2) is closed.

(1)

A. will 1FV-1150 B. will 1HV-7600 C. will NOT 1FV-1150 D. will NOT 1HV-7600

51.

Initial conditions:

- Unit 2 reactor tripped.

- 19221-C, Response to Inadequate Core Cooling, was entered.

Current condition:

- The crew is depressurizing all intact SGs to 200 psig.

Which one of the following completes the following statement?

The depressurization of all intact SGs is stopped when SG pressures reach 200 psig to prevent A. excessive cooldown of the SG U-tubes B. injection of accumulator nitrogen into the RCS C. a pressurized thermal shock condition of the reactor vessel D. voiding in the reactor vessel head and loss of pressurizer level

52.

Initial conditions:

- Unit 1 is at 100% reactor power.

- TPCW pump #1 is in service.

- TPCCW pump #1 is in service.

- TPCCW heat exchanger #1 is in service.

Current condition:

- TPCW pump #1 breaker trips.

Which one of the following completes the following statements?

Over the next 30 minutes, TPCCW temperature (1 )_ expected to rise.

Any temperature changes in TPCCW will directly affect the _(2) Coolers.

(1)

A. is MFP Lube Oil B. is Main Generator Stator C. is NOT MFP Lube Oil D. is NOT Main Generator Stator

53.

Given the following:

- Unit 1 is at 100% reactor power.

- Turbine Plant Cooling Water (TPCW) flow and pressure lower due to a significant system leak.

Which one of the following completes the following statement?

With no operator action, the running rotary air compressor will trip due to (1 ),

and an emergency cooling water source to the air compressors is supplied from the (2) water system.

(1 )_

A. low cooling water pressure demin B. low cooling water pressure utility C. high discharge temperature demin D. high discharge temperature utility

54.

Initial condition:

- Both units are at 100% reactor power.

Current conditions:

- Unit 1 instrument air pressure is lowering.

- 18028-C, Loss of Instrument Air, is in progress.

- Unit 2 instrument air pressure is stable.

- Four air compressors total on both units are running.

(one air compressor on Unit 1, three air compressors on Unit 2)

Which one of the following completes the following statements?

Per 18028-C, the Unit 1 and Unit 2 instrument air headers _(1 )_ allowed to be cross-tied.

If the instrument air headers were cross-tied, the Unit 2 instrument air header (2) automatically isolate from the Unit 1 instrument air header in response to continuously lowering air header pressure.

(1 ) _(2)_

A. are would B. are would NOT C. are NOT would D. are NOT would NOT

55.

Initial condition:

- Both units are at 100% reactor power.

Current condition:

- North Fire Water Storage Tank empties due to a significant leak.

Which one of the following completes the following statement?

The normal makeup source to the Fire Water Storage Tanks is (1 ) water, and per 92040-C, Fire Protection Operability and LCO Requirements, Fire Protection LCO 4.3, Suppression System Operability, (2) met.

_(1 )_

A. well is B. well is NOT C. river is D. river is NOT

56.

Initial conditions:

- Unit 2 is at 100% reactor power.

- Rapid containment entry is in progress to check an RCP oil drain tank level.

Current condition:

- All containment lighting extinguishes.

Which one of the following completes the following statements?

Per 00303-C, Containment Entry, personnel inside containment _(1)_ required to immediately exit.

If the containment airlock inner door would NOT close when the personnel exited, the Tech Spec LCO 3.6.2, Containment Air Locks, Required Action would be to close the outer airlock door _(2)_.

(1)

A. are immediately B. are in no later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. are NOT immediately D. are NOT in no later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

57.

Initial conditions:

- Unit 1 is in a refueling outage.

- Core reload is in progress.

Current condition:

- The inner emergency air lock door is open and NOT capable of being closed.

Which one of the following completes the following statement?

Per Tech Spec 3.9.4, Containment Penetrations, the equipment hatch must be capable of being closed and held in place with a minimum of (1 ) bolts, and per Tech Spec 3.9.4, core reload (2) allowed to continue.

(1 )

A. 4 is B. 4 isNOT C. 8 is D. 8 isNOT

58.

Given the following:

- On-coming OATC is relieving the shift following 7 days off.

Which one of the following completes the following statement?

Per 10004-C, Shift Relief, the OATC is required to review, as a minimum, the narrative logs for the preceding _(1)_ days, and the OATC _(2)_ required to review all active Night Orders.

_(1 )_

A. 7 is B. 7 isNOT C. 3 is D. 3 i5NOT

59.

Given the following:

- Planned maintenance will cause multiple control room alarms.

- Expected alarms have been flagged.

Which one of the following completes the following statement?

Per NMP-OS-007-OO1, Conduct of Operations Standards and Expectations, for the expected alarms, subsequent recurring alarms associated with this same maintenance activity _(1 ) require a verbal announcement, and for the expected alarms, the associated ARP compensatory actions (2) required to be performed.

_(1 )_

A. do are B. do are NOT C. do NOT are D. do NOT are NOT

60.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- ALB1O-C05 RPI NON URGENT ALARM is received.

- DRPI Data A Failure LEDs are lit.

- General Warning LED for rod M12 is lit.

Which one of the following completes the following statement?

The purpose of the DRPI display console is to provide _(1)_ rod position indication, and based on the given conditions, the DRPI accuracy for rod M12 is (2)_ steps.

(1 )_ _(2)_

A. actual -10,+4 B. actual +10,-4 C. demanded -10,÷4 D. demanded +10,-4

61.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- Pressurizer Safety Valve A is declared inoperable due to a discrepancy found in previous test data.

Which one of the following completes the following statement?

Per Tech Spec LCO 3.4.10, Pressurizer Safety Valves, the required lift setting for the pressurizer safety valve is _(1)_ +/- 50 psig, and per Tech Spec LCO 3.4.10, the inoperable safety valve must be restored to OPERABLE status in no later than (2) or a unit shutdown will be required.

_(1 ) _(2)_

A. 2345 15 minutes B. 2345 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. 2460 15 minutes D. 2460 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

62.

Initial condition:

- Unit 2 reactor power is 12% with a shutdown in progress.

Current conditions:

- Intermediate Range N36 fails full-scale high.

- No operator action has been taken.

Which one of the following completes the following statement?

Based on the current conditions, an automatic reactor trip _(1) occur, and the P-6 SR HIGH FLUX TRIP block 2) require manual RESET when reactor power lowers below its associated reset setpoint.

_(1 )_ _(2)_

A. did will B. did will NOT C. did NOT will D. did NOT will NOT

63.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a SGTR on SG #3.

Current condition:

- 19030-C, Steam Generator Tube Rupture, is in progress.

Which one of the following completes the following statement?

Per 1 9030-C, the ruptured SG ARV lift setpoint is adjusted to (1 ),

and the reasons for this adjustment are to _(2).

A. (1) ll2Opsig (2) minimize radiation releases through the ARV and prevent lifting of MSSVs B. (1) 1120 psig (2) promote thermal stratification and prevent SG depressurization C. (1) ll6Opsig (2) minimize radiation releases through the ARV and prevent lifting of MSSVs D. (1) 1160 psig (2) promote thermal stratification and prevent SG depressurization

64.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- Containment entry is to be performed per 00303-C, Containment Entry.

Which one of the following completes the following statement?

Per 00303-C, the area inside the bioshield is posted as a _(1)_ Area, and per 00303-C, entry into the _(2)_ is prohibited.

(1 )_ _(2)_

A. Very High Radiation elevator B. Very High Radiation 261 foot mezzanine C. Locked High Radiation elevator D. Locked High Radiation 261 foot mezzanine

65.

Procedure titles as follows:

- 19000-C, Reactor Trip or Safety Injection

- 19100-C, Loss of All AC Power At time 1105:

- Unit 1 is in Mode 4.

- Multiple alarms are received on the QMCB and the QEAB.

Approximately 45 seconds later:

- Two of three white pot lights (left and center lights) are NOT lit on the QEAB for both 1 AAO2 and 1 BAO3.

- No operator action has been taken.

Which one of following completes the following statement?

Based on the current conditions, direct entry into 1) is required, and when performing the Immediate Operator Actions, the Reactor Trip Breaker status indication on the QMCB _(2)_ available.

_(1 ). _(2)_

A. 19000-C is B. 19000-C is NOT C. 19100-C is D. 19100-C is NOT

66.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- The crew is implementing EOPs following a reactor trip.

Which one of the following completes the following statement?

Per 10020-C, EOP and AOP Rules of Usage, when performing steps in the EOPs, the crew _(1 )_ required to complete each step before continuing to the next step, and continuous action steps that are skipped by procedure step transitions _(2)_

required to be applied.

_(1 )_

A. is are B. is are NOT C. is NOT are D. is NOT are NOT

67.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a SGTR.

Current conditions:

- Crew is initiating the Foldout Page of 1 9000-C, Reactor Trip or Safety Injection.

- Containment pressure is 1 .4 psig.

- All SG NR levels are 8% and rising.

Per 10020-C, EOP and AOP Rules of Usage, which one of the following completes the following statements?

Based on the given conditions, the UO (1) allowed to take early operator action to isolate AFW to the ruptured SG.

Shift Supervisor permission _(2)_ required prior to performing early operator actions.

(1 ) _(2)_

A. is is B. is is NOT C. is NOT is D. is NOT is NOT

68.

Initial conditions:

- Unit 2 reactor trip and Si occurred due to a faulted SG.

- 19020-C, Faulted Steam Generator Isolation, is in progress.

Current conditions:

- UO reports an uncontrolled level rise on SG #1.

- Crew transitions to 19005-C, Rediagnosis.

- Crew is at the step to Check if this procedure should be implemented.

Which one of the following completes the following statement?

CSFST monitoring 1) suspended while performing 19005-C, and the required conditions for implementation of 19005-C _(2)_ met.

(1 )

A. is are B. is are NOT C. is NOT are D. is NOT are NOT

69.

At time 1200:

- Unit 1 reactor trip and SI occurred due to a LOCA.

At time 1230:

- RCS WR Tcold is 510°F and stable.

- 19012-C, Post-LOCA Cooldown and Depressurization, is in progress.

- Crew is at the step to Initiate RCS cooldown to cold shutdown.

Which one of the following completes the following statement?

Per 19012-C, the crew (1) allowed to lower RCS WR Tcold to 425 °F over the next 30 minutes, and the RCS cooldown rate is limited to reduce tensile stresses on the _(2) reactor vessel wall.

_(1 )_ _(2)_

A. is outer B. is inner C. is NOT outer D. is NOT inner

70.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a LOCA.

Current condition:

- 19112-C, LOCA Outside Containment, is in progress.

Which one of the following completes the following statement?

Per 19112-C, to attempt to stop the leak the CCP discharge piping (1) be isolated, and the indication that will be used to determine when the inter-system LOCA has been isolated is (2)_.

(2)

A. will RCS WR pressure rising B. will Auxiliary Building rad monitors lowering C. will NOT RCS WR pressure rising D. will NOT Auxiliary Building rad monitors lowering

71 At time 1000:

- Unit 2 reactor tripped with a RED path on Heat Sink.

- 19231-C, Response to Loss of Secondary Heat Sink, is entered.

- Containment pressure is 1.8 psig.

- RCS pressure is 2290 psig.

- SGs #1 and #4 WR levels are 16%.

- SGs #2 and #3 WR levels are 37%.

- COP A is in service.

At time 1008:

- SGs #1 and #4 WR levels are 12%.

- SGs #2 and #3 WR levels are 31%.

- CETCs are 560 °F and slowly rising.

- MDAFW pump A has been returned to service.

Which one of the following completes the following statement?

Based on the given conditions, bleed and feed criteria (1) met, and when AFW flow is initially restored, feed flow rates _(2)_ limited to between 30 and 100 gpm to the selected SG.

(1 ). _(2).

A. are are B. are are NOT

0. are NOT are D. are NOT are NOT

72.

Initial conditions:

- Unit 1 reactor trip and SI occurred.

- 19121-C, Uncontrolled Depressurization of All Steam Generators, is in progress.

- SI is reset.

Current conditions:

- Crew is at the step to Check if RHR Pumps should be stopped.

- RAT lA de-energizes due to a fault.

- DG1A starts and re-energizes its associated bus.

- RCS pressure is 200 psig.

Which one of the following completes the following statement?

RHR pump A (1)_ required to be manually started, and the _(2)_ are required to be manually started.

_(1 )_

A. is Containment Coolers in high speed B. is Post-LOCA Cavity Purge Units C. is NOT Containment Coolers in high speed D. is NOT Post-LOCA Cavity Purge Units

73.

Initial conditions:

- Unit 1 reactor trip occurred.

- Both RATs de-energized due to a switchyard fire.

Current conditions:

- 19232-C, Response to Steam Generator Overpressure, is in progress.

- SG #2 pressure is 1250 psig.

- SG #2 NR level is 85%.

Which one of the following completes the following statements?

Per 19232-C, the UO is required to lower SG #2 pressure using _(1)_.

When SG NR level is greater than 92%, steam flow is NOT initiated because of the risk of (2).

.(1 ).

A. ARVs water hammer B. ARVs excessive steam dryer delta P C. steam dumps water hammer D. steam dumps excessive steam dryer delta P

74.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Containment Spray pump A is tagged out.

Current conditions:

- Large break LOCA occurs.

- 19010-C, Loss of Reactor or Secondary Coolant, is in progress.

- Containment Spray pump B trips.

- Containment pressure is 22 psig.

- Containment hydrogen concentration is 5.1%.

Which one of the following completes the following statement?

The preferred method for reducing containment hydrogen concentration is _(1 )_ the containment atmosphere, and a(n) (2)_ path entry condition exists for 19251-C, Response to High Containment Pressure.

_(1 )_

A. diluting RED B. diluting ORANGE C. purging RED D. purging ORANGE

75.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- Crew is evaluating CSFSTs.

Current conditions:

- Containment integrated dose is calculated to be Rads.

- 1 RE-002, Containment Low Range, is 800 mRlhour.

- 1 RE-003, Containment Low Range, is 875 mR/hour.

- Containment pressure is 3.5 psig.

Which one of the following completes the following statement?

Based on the given conditions, adverse EOP values _(1)_ required to be used, and per the major actions of 19253-C, Response to High Containment Radiation Level, the operators are required to verify (2)_ alignment.

(1 )

A. are CIA B. are CVI C. are NOT CIA D. are NOT CVI

ANSWER KEY REPORT for Test Test Form: 0 Answers

1. ID Points Type 0 1 002K6.03 1 1.00 MCS A 2 003K5.02 1 1.00 MCS D 3 003K6.04 1 1.00 MCS D 4 004K2.06 1 1.00 MCS B 5 004K5.30 1 1.00 MCS B 6 005K2.01 1 1.00 MCS B 7 006A3.03 1 1.00 MCS B 8 007A3.01 1 1.00 MCS A 9 OO7EK1.05 1 1.00 MCS B 10 OO8AA1.03 1 1.00 MCS D 11 008G2.4.4 1 1.00 MCS A 12 008K1.01 1 1.00 MCS A 13 OO9EA1,06 1 1.00 MCS A 14 010K4.021 1.00 MCS A 15 O11EK3.01 1 1.00 MCS C 16 011K2.021 1.00 MCS D 17 012A1,01 1 1.00 MCS B 18 012K6.03 1 1.00 MCS A 19 013A1.041 1.00 MCS C 20 013A4.02 1 1.00 MCS C 21 015AA2.11 1 1.00 MCS C 22 015K5.09 1 1.00 MCS A 23 016A4.01 1 1.00 MCS B 24 022A1.04 1 1.00 MCS A 25 022AK1.03 1 1.00 MCS D 26 024AA1.23 1 1.00 MCS D 27 025AK2.02 1 1.00 MCS A 28 026A4.05 1 1.00 MCS A 29 026AG2.4.46 1 1.00 MCS B 30 029EA2.05 1 1.00 MCS B 31 033A3.02 1 1.00 MCS D 32 034K1.04 1 1.00 MCS A 33 035K3.01 1 1.00 MCS B 34 036AK3.03 1 1.00 MCS B 35 038EK1.02 1 1.00 MCS B 36 039A2.04 1 1.00 MCS A 37 039K5.08 1 1.00 MCS D 38 054AK3.04 1 1.00 MCS A 39 056AA2.20 1 1.00 MCS D 40 057AG2.4.35 1 1.00 MCS D 41 059AG2.1.23 1 1.00 MCS A 42 059G2.4,11 1 1.00 MCS B 43 061K6.01 1 1.00 MCS C 44 062AK3.01 1 1.00 MCS D 45 062K1.04 1 1.00 MCS C 46 063K1.03 1 1.00 MCS B Monday, September 28, 2015 10:33:23AM

{cH JL ct-/5 ANSWER KEY REPORT for Test Test Form: 0 Answers

1. ID Points Type 0 47 064A4.01 1 1.00 MCS D 48 065AA1.04 1 1.00 MCS D 49 071A1,061 1.00 MCS D 50 073A2.02 1 1.00 MCS A 51 074EA1.17 1 1.00 MCS B 52 076K3.01 1 1.00 MCS C 53 078K4.03 I 1.00 MCS D 54 079K4.01 1 1.00 MCS B 55 086G2.2.22 1 1.00 MCS B 56 103A2.05 1 1.00 MCS B 57 103K3.03 1 1.00 MCS A 58 G2.1.15 1 1.00 MCS C 59 G2.1.17 1 1.00 MCS C 60 G2.1.27 1 1.00 MCS B 61 G2.2.42 1 1.00 MCS C 62 G2.2.44 1 1.00 MCS C 63 G2.3.11 1 1.00 MCS C 64 G2.3.12 1 1.00 MCS A 65 G2.4.1 1 1.00 MCS C 66 G2.4.14 1 1.00 MCS C 67 G2.4.37 1 1.00 MCS C 68 WEO1EK2.01 1 1.00 MCS C 69 WEO3EA2.02 1 1.00 MCS D 70 WEO4EK2.01 1 1.00 MCS C 71 WEO5EK2.02 I 1.00 MCS D 72 WE12EG2.4.20 1 1.00 MCS B 73 WE13EK3.04 1 1.00 MCS A 74 WE14EK1.02 1 1.00 MCS B 75 WE16EA2.02 1 1.00 MCS D SECTION 1 (75 items) 75.00 Monday, September 28, 2015 10:33:23 AM 2

HL2O NRC RO Exam Provided References Index

1. EOP 19030-C Step 50 Control RCS Pressure and Charging

2. AOP 18016-C Attachment 1 Turbine Load Restrictions based on Steam Flow

1.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- 1 NAA de-energized due to a fault.

Current conditions:

- 19200-C, Critical Safety Function Status Trees, is initiated.

- RCS pressure is 1800 psig and stable.

- All RCP 1 E breaker handswitch red lights are lit.

- RCPs #2 and #4 non-i E breaker handswitch red lights are lit.

- RCPs #1 and #3 non-i E breaker handswitch green lights are lit.

Which one of the following completes the following statement?

The RVLIS dynamic range level indication _(i )_ providing accurate input to the Core Cooling status tree, and the RVLIS level indication (2) density compensated.

_(1 )_ _(2)_

A. is is B. is is NOT C. is NOT is D. is NOT is NOT

2.

Initial conditions:

- Unit 1 is at 20% reactor power following an outage.

- 12004-C, Power Operation (Mode 1), is in progress.

Current conditions:

- An automatic reactor trip occurred due to a grid disturbance.

- 19001-C, Reactor Trip Response, is in progress.

- All RCP 1 E breakers are open.

- All RCP non-1 E breakers are closed.

Which one of the following completes the following statement?

The reactor automatically tripped due to (1),

and per the bases of Tech Spec LCO 3.3.1, RTS Instrumentation, this automatic reactor trip ensures (2).

A. (1) RCS two loop low flow (2) the RCPs are protected from excessive current B. (1) RCS two loop low flow (2) sufficient RCP coastdown time to avoid violating DNBR C. (1) RCP underirequency (2) the RCPs are protected from excessive current D. (1) RCP underfrequency (2) sufficient RCP coastdown time to avoid violating DNBR

3.

Initial conditions:

- Unit 2 is at 100% reactor power.

- 2BY1 B is de-energized due to a fault.

Current condition:

- Unit 2 reactor trip and SI occur due to a LOCA.

Which one of the following completes the following statement?

ACCW flow to the RCP thermal barrier _(1) isolated, and RCP seal return flow is currently being directed to the _(2)_.

(1 )

A. is VCT B. is PRT C. is NOT VCT D. is NOT PRT

4.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Letdown flow is 120 gpm.

- Pressurizer level control is selected to CH 459 / 460.

Current conditions:

- One 120 VAC vital bus de-energized.

- Letdown flow remains at 120 gpm.

Which one of the following identifies the specific 120 VAC vital bus that de-energized?

A. 1AY1A B. 1AY2A C. 1BY1B D. 1BY2B

5.

Initial conditions:

- Unit 1 is in Mode 5 on solid plant pressure control.

- RHR Train A is in service for temperature control.

- RHR letdown is in service.

- 1 FIC-1 21, Charging Line Control, is in manual.

- 1PIC-131, LP Letdown Control, is in manual.

Current condition:

- CCW Train A pumps trip on low surge tank level.

Which one of the following completes the following statement?

Over the next 10 minutes with no operator action, letdown flow rate will _(1 )_,

and charging flow rate will (2).

(1)

A. rise rise B. rise lower C. lower rise D. lower lower

6.

Initial conditions:

- Unit 2 is in Mode 4.

- RHR Train A is aligned for ECCS injection.

- RHR Train B is in service for temperature control.

- 2BA03 is energized by the SAT.

Current conditions:

- Both RATs de-energize due to a lightning strike.

- Plant Wilson is NOT affected.

Which one of the following completes the following statement?

The 4160 VAC bus breaker supplying RHR pump A is _(1)_,

and the 4160 VAC bus breaker supplying RHR pump B is (2).

(1 ).

A. open open B. open closed C. closed open D. closed closed

7.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- Unit 1 reactor trip and SI occurs.

Which one of the following completes the following statement?

The white indicating lights on handswitches 1 HS-8508A and B, CCP RV to RWST Isolation, _(1)_ lit, and their associated valves, 1 HV-8508A and B, will operate automatically in response to input from a(an) _(2)_ pressure transmitter signal.

_(1 )_ _(2).

A. are RCSWR B. are CCP discharge C. are NOT RCSWR D. are NOT CCP discharge

8.

Initial conditions:

- Unit2isin Mode 5.

- RHR Train A is in service for shutdown cooling.

Current condition:

- ALB12-E02 PRZR REL TANK HI PRESS is received.

Which one of the following completes the following statement?

The RHR pump A (1) relief valve lifting will cause the PRT high pressure condition, and with no operator action, 2P1-469, PRT Pressure, on the QMCB will reach a maximum of (2) psig before the rupture disk fails.

(1 )

A. suction 100

8. suction 1 15 C. discharge 100 D. discharge 115

9.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- Unit 1 reactortrips.

- Steam dumps are NOT available.

- RCS Tavg is stable and controlled by the ARVs in automatic.

Which one of the following completes the following statement?

Over the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, with no operator action, ARV controller demand output will A. rise B. lower C. remain the same D. rise and then lower

10.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a pressurizer steam space leak.

- 1901 2-C, Post-LOCA Cooldown and Depressurization, was entered.

Current conditions:

- Crew is at the step to Initiate RCS cooldown to cold shutdown.

- Steam dumps are in the Steam Pressure Mode.

Which one of the following completes the following statement?

Per 19012-C, the RCS cooldown rate will be monitored using RCS _(1)_ leg temperatures, and per 19012-C, the cooldown is initiated by (2) demand on 1 PIC-507, Steam Dump Control.

_(1 )_ _(2)_

A. hot lowering B. hot raising C. cold lowering D. cold raising

11.

Initial conditions:

- Unit 1 is at 100% reactor power.

- CCW Train A is in service.

- ALB36-A01 4160V SWGR 1AA02 TROUBLE is received and does NOT clear.

- Multiple CCW Train A low pressure and low flow alarms are received, then clear.

Current condition:

- CCW Train A pressure and flow are normal and stable.

Which one of the following completes the following statement?

One CCW Train A pump has experienced a (1),

and entry into 18020-C, Loss of Component Cooling Water, _(2)_ required.

_(1 )_

A. locked rotor is B. locked rotor is NOT C. sheared shaft is D. sheared shaft is NOT

12.

Initial conditions:

- Unit 2 is at 100% reactor power.

- ACCW pump #2 is in service.

- ACCW pump #1 is in standby.

Current conditions:

- NSCW Train B is shut down due to a piping break.

- No other operator action has been taken.

Which one of the following completes the following statement?

Cooling _(1)_ being provided to the ACCW pump #2 motor, and cooling (2)_ being provided to the ACCW system loads.

_(1 )_

A. is is B. is is NOT C. is NOT is D. is NOT is NOT

13.

Given the following:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- 19010-C, Loss of Reactor or Secondary Coolant, is in progress.

- OATC is assigned to monitor CSFSTs per 19200-C, Critical Safety Function Status Trees.

Which one of the following completes the following statement?

To ensure the CSFSTs are indicating correctly for the given plant conditions, the OATC is required to verify the IPC indicates Mode (1),

and on the IPC, an active CSFST RED path is depicted by a _(2)_ line.

(1 )

A. 0 solid B. 0 hollow C. 3 solid D. 3 hollow

14.

Initial conditions:

- Unit 1 is at 25% reactor power.

- All pressurizer backup heaters are in automatic.

- Variable pressurizer heaters are in the ON position.

- Due to a pressurizer level control malfunction, pressurizer level lowers to 15%

and pressurizer pressure lowers to 2180 psig.

Current conditions:

- Pressurizer level is 25% and slowly rising.

- Pressurizer pressure has returned to 2215 psig.

Which one of the following completes the following statement?

Assuming no operator action, the pressurizer variable heaters are (1 )_,

and the pressurizer backup heaters are _(2)_.

_(1 )_ _(2)_

A. off off B. oft on C. on off D. on on

15.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a large break LOCA.

Current conditions:

- 19000-C, Reactor Trip or Safety Injection, UO Initial Actions are in progress.

- Containment pressure is 22.5 psig.

Which one of the following completes the following statement?

For the given conditions, the main steam lines are verified isolated to (1 )_,

and handswitch 1 HS-3007A, SLI Actuation, (2) send an actuation signal to the Train B MSIVs and Train B BSIVs.

A. (1) prevent a return to criticality (2) will B. (1) prevent a return to criticality (2) will NOT C. (1) distinguish between a primary and secondary break (2) will D. (1) distinguish between a primary and secondary break (2) will NOT

16.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Loss of off-site power to 1AAO2 and 1 BAO3 occurs.

Current conditions:

- DG1 B starts, re-energizes its associated bus, and completes the loading sequence.

- DO1A will NOT start.

Which one of the following completes the following statements?

The power supplies to the Tech Spec pressurizer heater groups are (1 ).

Based on the current conditions, Tech Spec LCO 3.4.9, Pressurizer, _(2)_ met.

(1 )_ (2)

A. 1 NBO8 and 1 NBO9 is B. 1 NBO8 and 1 NBO9 is NOT C. 1NBO1 and 1NB1O is D. 1NBO1 and 1NB1O is NOT

17.

Initial condition:

- Unit 2 is at 70% reactor power.

Current conditions:

- Pressurizer pressure control malfunction causes pressurizer pressure to rise.

- RCS Tavg is constant.

Which one of the following completes the following statement?

Based on the given conditions, the CT delta T reactor trip setpoint will _(1 )_,

and the OP delta T reactor trip setpoint will (2).

_(1 )_

A. rise rise B. rise not change C. lower rise D. lower not change

18.

Initial conditions:

- Unit 1 is at 100% reactor power.

- 1 PT-456, Pressurizer Pressure, fails off-scale high.

Current condition:

- All bistables associated with 1 PT-456 have been placed in their Tech Spec required state.

Which one of the following completes the following statement?

The minimum number of additional Pressurizer Pressure channels failing high required to initiate a reactor trip is (1 ),

and the minimum number of additional Pressurizer Pressure channels failing low required to initiate a safety injection is (2)_.

(1 )

A. 1 1 B. 1 2 C. 2 1 D. 2 2

19.

Initial conditions:

- Unit 1 reactor tripped from 35% reactor power.

- MFP A is running.

Current conditions:

- 19001-C, Reactor Trip Response, is in progress.

- Crew is at Step 4 to Limit RCS Cooldown.

- SG NR levels are 33% in each SG.

- MDAFW flow is throttled to 50 gpm to each SG.

Which one of the following completes the following statement?

Based on the current conditions, when the UO trips MFP A, the MDAFW pump discharge valves will (1),

and the MDAFW pump discharge valves handswitch white lights (2)_ be lit.

(1 ). _(2).

A. re-open fully will B. re-open fully will NOT C. remain throttled will D. remain throttled will NOT

20.

Initial condition:

- Unit 2 reactor trip and SI occurred due to a LOCA.

Current conditions:

- Reactor Trip Breaker B will NOT open.

- RCS pressure is 22 psig.

Which one of the following completes the following statement?

The Train B SI signal (1) be reset, and the Train B CVI signal _(2)_ be reset.

_(1 )_ _(2)_

A. can can B. can can NOT C. can NOT can D. can NOT can NOT

21.

Initial conditions:

- Unit 1 reactor is tripped due to a total loss of ACCW.

- All RCPs are stopped.

- 19221-C, Response to Inadequate Core Cooling, is in progress.

Current conditions:

- SGs are depressurized to less than 200 psig.

- CETCs are 1220°F and rising.

- SG #1 NR level is 40%.

- The crew is at the step to Check if an idle RCS cooling loop is available.

Which one of the following completes the following statement?

Based on the given conditions, normal RCP support conditions (1 ) required prior to starting an available RCP, and 19221-C requires a minimum SC NR level in an idle RCS loop prior to starting an RCP to minimize the risk of _(2)_.

_(1 )_ _(2).

A. are creep rupturefailure B. are pressurized thermal shock C. are NOT creep rupture failure D. are NOT pressurized thermal shock

22.

Initial conditions:

- Unit 1 is at 90% reactor power.

- All control systems are in automatic.

- Power Range N41 fails high.

Current condition:

- 18002-C, Nuclear Instrumentation System Malfunction, is entered.

Which one of the following completes the following statements?

Based on the given conditions, automatic rod motion (1 ) occur.

Per 18002-C, the Movable Incore Detector System _(2)_ used to confirm QPTR.

_(1 )_ _(2)_

A. did is B. did is NOT C. did NOT is D. did NOT is NOT

23.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- One Loop 1 NR temperature instrument fails low.

Which one of the following completes the following statement?

To remove the Loop 1 Tavg input to the rod control system, the operator is required to and completing this action _(2)_ remove the Loop 1 Tavg input to the Low Tavg Feedwater Isolation (FWI) circuit.

A. (1) place 1 TS-41 2T, Tavg Defeat Sel switch, to the affected loop (2) will B. (1) place 1TS-412T, Tavg Defeat Sel switch, to the affected loop (2) will NOT C. (1) trip the associated temperature instruments bistables (2) will D. (1) trip the associated temperature instruments bistables (2) will NOT

24.

Initial conditions:

- Unit 1 reactor tripped due to an inadvertent SI.

- All equipment automatically aligned as required.

Current conditions:

- SI has been reset.

- NSCW Train A header pressure is lowering.

- NSCW Train A return header flow is lowering.

- Containment sump levels are rising.

Which one of the following completes the following statement?

Based on the given conditions, a rupture has occurred in the cooling coils of a (1 ) Cooling Unit, and NSCW flow to the leaking Cooling Unit _(2) be isolated from the QMCB.

(1)

A. Containment can B. Containment can NOT C. Reactor Cavity can D. Reactor Cavity can NOT

25.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- The following alarms are received:

- ALBO7-A05 REGEN HX LTDN HI TEMP

- ALBO7-B06 CHARGING LINE HI / LO FLOW

- ALBO7-D03 LTDN HX OUT HI TEMP

- ALBO8-F06 RCP SEAL WATER INJ LO FLOW

- No operator action has been taken.

Which one of the following completes the following statement?

Based on the given conditions, (1) has failed closed, and pressurizer level is _(2)_.

_(1 )

A. 1 HV-1 82, Seal Flow Control rising B. 1 HV-1 82, Seal Flow Control lowering C. 1 FV-121, Charging Flow Control rising D. 1 FV-1 21, Charging Flow Control lowering

26.

Initial conditions:

- Unit 2 is at 70% reactor power.

- Control rods are stepping out without demand.

- Reactor will NOT trip from the QMCB.

- 1921 1 -C, Response to Nuclear Power Generation / ATWT, is entered.

- Boric Acid Transfer Pump (BATP) A is started to establish emergency boration.

Current condition:

- BATP A trips.

Which one of the following completes the following statement?

BATP B _(1 )_ automatically start when BATP A trips, and per 19211-C, the minimum charging flow is required to be greater than (2) gpm as indicated on 2Fl-121, Charging Flow.

(1 ) _(2)_

A. will 30 B. will 42 C. will NOT 30 D. will NOT 42

27.

Initial conditions:

- Unit 1 is in Mode 5.

- RHR pump A is in service for shutdown cooling.

Current conditions:

- RCS level is 187 feet and lowering due to a leak.

- RCS temperature is 190 °F.

- 18019-C, Loss of Residual Heat Removal, is in progress.

Which one of the following completes the following statements?

Per 18019-C, the operating crew(1) required to stop RHR pump A.

Per 18019-C, if no pump is available, the preferred gravity drain path to restore inventory is through the (2) pumps to the RCS cold legs.

_(1 )_

A. is RHR B. is SI C. is NOT RHR D. is NOT SI

28.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- OATC manually actuated Containment Spray (CS) from the QMCB C panel.

Current condition:

- Containment pressure is 23.8 psi.

9 Which one of the following completes the following statement?

To manually actuate CS, the OATC 1) required to simultaneously operate both CS Actuation handswitches, 1 HS-4001 0 and 1 HS-4001 1, on the C panel, and based on the current condition, if the OATC takes both the CS Reset handswitches to the RESET position, the CS actuation signal _(2)_ reset.

_(1 )_ _(2).

A. was will B. was will NOT C. was NOT will D. was NOT will NOT

29.

Initial conditions:

- Unit 1 is at 100% reactor power.

- CCW pumps #1 and #3 are running.

Current conditions:

- ALBO2-A05 COW TRAIN A SURGE TK LO-LO LVL is received.

- CCW pump #3 trips.

- CCW pump #lis running.

- The following alarms are received:

- ALBO2-A06 CCW TRAIN A LO HDR PRESS

- ALBO2-B06 CCW TRAIN A LO FLOW

- ALBO2-D06 COW TRAIN A RHR HX LO FLOW

- ALBO2-E05 CCW TRAIN A RHR PMP SEAL LO FLOW Which one of the following completes the following statement?

COW pump #3 (1) trip due to a COW Train A Surge Tank level transmitter tailing low, and the standby COW pump will automatically start due to low CCW header (2).

_(1 ).. _(2)_

A. did flow B. did pressure C. did NOT flow D. did NOT pressure

30.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Containment mini-purge is in service for pressure relief.

Current conditions:

- Unit 1 experiences an ATWT.

- 1921 1-C, Response to Nuclear Power Generation / ATWT, is in progress.

- Crew is at the step to Check Containment Ventilation Isolation.

- Train A CVI MLBs are lit.

- Train B CVI MLB5 are NOT lit.

Which one of the following completes the following statement?

Based on the current conditions, the mini-purge flow path from containment (1) isolated, and per 19211-C, the Train _(2)_ CVI dampers and valves are required to be closed manually.

(1) (2)

A. is A B. is B C. is NOT A D. is NOT B

31.

Initial conditions:

- A fuel shuffle is in progress on Unit 2.

- All SEP cooling pumps are in service.

Current condition:

- Unit 2, SEP cooling pump A seal fails.

Which one of the following completes the following statement?

With no operator action, SEP inventory loss will stop due to uncovering the _(1)_,

and SEP water level _(2)_ remain above the minimum required by Tech Spec LCO 3.7.15, Euel Storage Pool Water Level.

(1 )

A. siphon breaker will B. siphon breaker will NOT C. pump suction piping will D. pump suction piping will NOT

32.

Initial conditions:

- Unit us in Mode 6 for a refueling outage.

- Control rod latching and verification is in progress.

- Source Range N31 is providing audible indication.

Current condition:

- Source Range N32 fails low.

Which one of the following completes the following statements?

TR 13.9.6, Source Range Monitor Audible Indication, (1) met.

t Based on the given conditions, core alterations are required to be suspended _(2)_.

_(1 )_

A. is immediately B. is in no later than 15 minutes C. is NOT immediately D. is NOT in no later than 15 minutes

33.

Initial conditions:

- Unit 1 is in Mode 3.

- A steam leak is reported in the Turbine Building.

Current condition:

- The UO actuates SLI.

Which one of the following completes the following statement?

A steam line break has the greatest reactivity impact on the reactor at the (1 ) of core life, and assuming no additional operator action, RCS temperature will stabilize at approximately (2)_ °F.

_(1 )_ _(2)_

A. end 557 B. end 561 C. beginning 557 D. beginning 561

34.

Initial condition:

- Fuel shuffle is in progress in the Unit 2 SEP.

Current conditions:

- An irradiated fuel assembly is dropped.

- ARE-2532A and B are in high alarm.

- 18006-C, Fuel Handling Event, is entered.

Which one of the following completes the following statement?

Per 18006-C, to ensure proper FHB HVAC alignment, the UO is required to (1) one FHB Post-Accident Exhaust unit, and establishing this required alignment is done to limit the _(2).

(1 ) _(2)..

A. stop airborne concentrations in the FHB B. stop off-site release C. start airborne concentrations in the FHB D. start off-site release

35.

Initial conditions:

- Unit 2 reactor trips due to a 175 gpm SGTR on SG #1.

- RCS pressure is 2100 psig.

- SG #1 pressure is 990 psig.

- 1 9030-C, Steam Generator Tube Rupture, is entered.

Current conditions:

- RCS pressure is 1260 psig.

- SG #1 pressure is 1120 psig.

- SG #1 NR level is 81% and slowly rising.

- Pressurizer level is 76%.

- Containment pressure is 0.1 psig.

- Crew is at the step to Control RCS pressure and charging flow to minimize RCS-to-secondary leakage.

Which one of the following completes the following statement?

The current SG leak rate is approximately (1 ) gpm, and based on the current conditions, the OATC _(2)_ required to continue depressurization of the RCS to control primary to secondary leakage.

REFERENCES PROVIDED A. 80 is B. 80 is NOT C. 135 is D. 135 is NOT

36.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- 1 PT-506, Turbine Power, fails low.

Which one of the following completes the following statement?

The QMCB B panel STEAM DUMP ARMED light on ZLB-2 _(1)_ be lit, and per 18001-C, Systems Instrumentation Malfunction, the steam dumps (2) required to be placed in the Steam Pressure Mode.

(1)

A. will are B. will are NOT C. will NOT are D. will NOT are NOT

37.

Initial conditions:

- Unit 1 experienced an ATWT at EOL conditions.

- 1921 1 -C, Response to Nuclear Power Generation / ATWT, is in progress.

Current conditions:

- Emergency Boration can NOT be established.

- Crew is at Step 23 to Check reactor power.

- Reactor power is 8%.

- IR SUR is negative.

- RCS temperature is 563 °F and slowly rising.

- RCS pressure is 2285 psig.

Which one of the following completes the following statement?

Based on the given conditions, per 19211-C, the crew (1) required to dump steam to lower RCS temperature, and per 19211-C, the RCPs (2) required to be stopped.

_(1 )_ _(2)_

A. is are B. is are NOT C. is NOT are D. is NOT are NOT

38.

Initial conditions:

- Unit 1 reactor tripped due to a loss of feedwater.

- Reactor Trip Breaker A is NOT open.

- Reactor Trip Breaker B is open.

Current conditions:

- 19231-C, Response to Loss of Secondary Heat Sink, is in progress.

- RCS bleed and feed is in progress.

- The crew is re-establishing feedwater using a MFP.

Which one of the following completes the following statement?

The Bypass Feedwater Isolation Valves (BFIV5) were closed (1),

and to re-establish feedwater flow, the Reactor Trip Breakers are cycled to allow the

_(2) signal to be reset.

A. (1) automatically due to the Feedwater Isolation (FWI) signal (2) FWI B. (1) automatically due to the Feedwater Isolation (FWI) signal (2) SI C. (1) manually by the UO when verifying FW isolation valves closed (2) FWI D. (1) manually by the UO when verifying FW isolation valves closed (2) SI

39.

Initial conditions:

- Unit 1 is at 100% reactor power.

- RAT lA de-energizes due to a fault.

- DG1A starts and re-energizes its associated bus.

- Load sequencing is complete.

Current conditions:

- 18031-C, Loss of Class 1 E Electrical Systems, is entered.

- Unit 1 reactor power is 100.8%.

- AFW flow indications are as follows:

- SG#1 is4o8gpm.

- SC #2 is4logpm.

- SC #3 is4o5gpm.

- SG#4is4o6gpm.

- No operator action has been taken.

Which one of the following completes the following statement?

To lower TDAFW pump flow, the UO will use the (1 ) control mode on controller 1 PDIC-51 80A, TDAFW Cntl Delta P-Feed to Stm, and the MDAFW pumps _(2)_ operating as expected for the given conditions.

(1 ). _(2)_

A. delta-P are B. delta-P are NOT C. speed are D. speed are NOT

40.

Initial conditions:

- Unit 1 is at 100% reactor power.

- 1 BY2B is de-energized.

Current condition:

- Systems Operator transferred 1 BY2B to its alternate power source.

Which one of the following completes the following statements?

The alternate power source for 1 BY2B is a(n) (1).

If off-site power is lost, based on the current conditions the Train B sequencer (2)_

start DG1B.

(1 ) _(2)_

A. inverter will B. inverter will NOT C. regulated transformer will D. regulated transformer will NOT

41.

Initial conditions:

- Unit 1 is in a refueling outage.

- Turbine building drains are being pumped down.

Current condition:

- 1 RE-0848, Turbine Building Drains, is in high alarm.

Which one of the following completes the following statement?

The turbine building normal drain flow path (1)_ automatically isolate, and per 17100-1, Annunciator Response Procedure for the Process and Effluent Radiation Monitoring System (RMS), the Systems Operator is required to verify that the turbine building drains are aligned to the _(2).

_(1 )

A. will Dirty Drain Tank B. will Waste Water Retention Basin C. will NOT Dirty Drain Tank D. will NOT Waste Water Retention Basin

42.

Initial conditions:

- Unit 2 is at 100% reactor power.

- Feedwater heaters 4A and 5A extraction steam valves fail closed due to a common mode failure.

Current conditions:

- 18016-C, Condensate and Feedwater Malfunction, is in progress.

- Operators reduced turbine load and power is stable at 100% RTP.

Which one of the following completes the following statement?

During the initial loss of feedwater heaters, the PR Nis will indicate (1) than actual reactor power, and per 18016-C, the operators (2) required to commence additional turbine load reduction.

REFERENCES PROVIDED (1 )

A. lower are B. lower are NOT C. higher are D. higher are NOT

43.

Initial conditions:

- Unit 1 experienced a loss of heat sink.

- TDAFW pump governor developed a hydraulic oil leak.

- TDAFW pump tripped on overspeed.

- 1 HS-1 5111, TDAFW Trip and Throttle Valve, green and amber lights are lit.

Current condition:

- OAO is dispatched to reset the TDAFW pump mechanical overspeed trip.

Which one of the following completes the following statement?

The amber light on 1HS-15111 will extinguish when _(1)_,

and with the failed governor valve, the TDAFW pump (2) be operated locally.

A. (1) 1 HS-51 06A, TDAFW Steam Supply, is taken to the close position (2) can B. (1) 1 HS-51 06A, TDAFW Steam Supply, is taken to the close position (2) can NOT C. (1) the mechanical trip linkage is manually reset (2) can D. (1) the mechanical trip linkage is manually reset (2) can NOT

44.

Initial conditions:

- Unit 1 is at 100% reactor power.

- NSCW Train A was shutdown due to the loss of pumps #3 and #5.

Current conditions:

- NSCW pump #3 has been repaired.

- NSCW pumps #1 and #3 are being started simultaneously from standby.

Which one of the following completes the following statement?

NSCW Train A discharge header is repressurized by _(1)_,

and this method of repressurization is designed to limit _(2)_.

(1 )

A. its discharge valve throttling DG1A current B. its discharge valve throttling water hammer C. flow through a bypass line DG1A current D. flow through a bypass line water hammer

45.

Initial conditions:

- Unit 1 is operating at 60% reactor power with a plant startup in progress.

- ACCW pump #1 is in service.

Current conditions:

- Both Unit 1 RATs de-energize.

- Both DGs start and re-energize their respective buses.

- No other switchyard components are affected.

Which one of the following completes the following statement?

With no operator action, one minute after the RATs de-energize, the Reactor Trip Breakers will be (1),

and per 18031-C, Loss of Class 1 E Electrical Systems, the crew is required to (2) one ACCW pump.

(1 )

A. open stop B. open start C. closed stop D. closed start

46.

Initial conditions:

- Unit 1 is at 100% reactor power.

- A loss of off-site power occurs.

Current conditions:

- DG1A starts and re-energizes its associated bus.

- DG1 B will NOT start.

- 1 BD1 bus voltage is 103 VDC.

Which one of the following completes the following statements?

Two battery chargers in service on 1 BD1 _(1) the normal operational alignment.

Based on the given conditions, per 18031-C, Loss of Class 1 E Electrical Systems, the minimum required action is to 2).

A. (1) is (2) open its associated battery breaker B. (1) is (2) shutdown its associated inverter and then open its battery breaker C. (1) is NOT (2) open its associated battery breaker D. (1) is NOT (2) shutdown its associated inverter and then open its battery breaker

47.

Given the following:

- Unit 1 is at 100% reactor power.

- DG1A is paralleled to the grid and loaded to 7000 kW.

Which one of the following completes the following statement?

Based on the given conditions, DG1A (1) operating in the UNIT mode, and to directly change the kVAR / reactive loading of DG1A, the UO is required to depress the 2)_ CONTROL pushbuttons on the QEAB.

(1 ).. _(2)_

A. is SPEED B. is VOLTAGE C. is NOT SPEED D. is NOT VOLTAGE

48.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- 1 P1-9377, Service Air Header Pressure, is 92 psig and slowly lowering.

- 18028-C, Loss of Instrument Air, is in progress.

Which one of the following completes the following statement?

Based on the given conditions, 1 PV-9375, Service Air Dryer Inlet Isolation Valve, (1) closed, and per 18028-C, a Systems Operator will be dispatched to manually align a back-up

_(2)_ to supply the River Intake Air System.

.(1 ).

A. is nitrogen bottle B. is air compressor C. is NOT nitrogen bottle D. is NOT air compressor

49.

Initial conditions:

- Unit 1 transfer of Gas Decay Tank #2 contents to Gas Decay Tank #4 is in progress.

- Auxiliary Building Supply and Exhaust HVAC is in service.

Current conditions:

- 1 RE-0039A, Waste Gas Decay Tank Radiogas, is in high alarm.

- 1 RE-0039B, Waste Gas Compressor Radiogas, is in high alarm.

- 1 RE-12442C, Plant Vent Radiogas Particulate (Low Range), is in high alarm.

Which one of the following completes the following statement?

Per 17100-C, Annunciator Response Procedure for the Process and Effluent Radiation Monitoring System (RMS), the operators are required to (2).

A. manually start the Piping Penetration Units B. manually secure all Auxiliary Building HVAC C. manually secure only the Auxiliary Building Normal Supply Units D. continue monitoring radiation levels, but no additional action associated with Auxiliary Building HVAC is required

50.

Valve names as follows:

- 1 FV-1 150, Blowdown In let Isolation Valve

- 1 HV-7600, Blowdown Recycle Isolation Valve Initial condition:

- Unit 1 is at 100% reactor power.

Currrent condition:

- 1 RE-0021, SG Blowdown Liquid, fails high.

Which one of the following completes the following statement?

Unit 1 thermal power, as indicated by UQ-1 118, (1) be affected by the failure, and per 17100-1, Annunciator Response Procedure for the Process and Effluent Radiation Monitoring System (RMS), the operators will verify that blowdown isolation valve (2) is closed.

(1)

A. will 1FV-1150 B. will 1HV-7600 C. will NOT 1FV-1150 D. will NOT 1HV-7600

51.

Initial conditions:

- Unit 2 reactor tripped.

- 19221-C, Response to Inadequate Core Cooling, was entered.

Current condition:

- The crew is depressurizing all intact SGs to 200 psig.

Which one of the following completes the following statement?

The depressurization of all intact SGs is stopped when SG pressures reach 200 psig to prevent A. excessive cooldown of the SG U-tubes B. injection of accumulator nitrogen into the RCS C. a pressurized thermal shock condition of the reactor vessel D. voiding in the reactor vessel head and loss of pressurizer level

52.

Initial conditions:

- Unit 1 is at 100% reactor power.

- TPCW pump #1 is in service.

- TPCCW pump #1 is in service.

- TPCCW heat exchanger #1 is in service.

Current condition:

- TPCW pump #1 breaker trips.

Which one of the following completes the following statements?

Over the next 30 minutes, TPCCW temperature (1 )_ expected to rise.

Any temperature changes in TPCCW will directly affect the _(2) Coolers.

(1)

A. is MFP Lube Oil B. is Main Generator Stator C. is NOT MFP Lube Oil D. is NOT Main Generator Stator

53.

Given the following:

- Unit 1 is at 100% reactor power.

- Turbine Plant Cooling Water (TPCW) flow and pressure lower due to a significant system leak.

Which one of the following completes the following statement?

With no operator action, the running rotary air compressor will trip due to (1 ),

and an emergency cooling water source to the air compressors is supplied from the (2) water system.

(1 )_

A. low cooling water pressure demin B. low cooling water pressure utility C. high discharge temperature demin D. high discharge temperature utility

54.

Initial condition:

- Both units are at 100% reactor power.

Current conditions:

- Unit 1 instrument air pressure is lowering.

- 18028-C, Loss of Instrument Air, is in progress.

- Unit 2 instrument air pressure is stable.

- Four air compressors total on both units are running.

(one air compressor on Unit 1, three air compressors on Unit 2)

Which one of the following completes the following statements?

Per 18028-C, the Unit 1 and Unit 2 instrument air headers _(1 )_ allowed to be cross-tied.

If the instrument air headers were cross-tied, the Unit 2 instrument air header (2) automatically isolate from the Unit 1 instrument air header in response to continuously lowering air header pressure.

(1 ) _(2)_

A. are would B. are would NOT C. are NOT would D. are NOT would NOT

55.

Initial condition:

- Both units are at 100% reactor power.

Current condition:

- North Fire Water Storage Tank empties due to a significant leak.

Which one of the following completes the following statement?

The normal makeup source to the Fire Water Storage Tanks is (1 ) water, and per 92040-C, Fire Protection Operability and LCO Requirements, Fire Protection LCO 4.3, Suppression System Operability, (2) met.

_(1 )_

A. well is B. well is NOT C. river is D. river is NOT

56.

Initial conditions:

- Unit 2 is at 100% reactor power.

- Rapid containment entry is in progress to check an RCP oil drain tank level.

Current condition:

- All containment lighting extinguishes.

Which one of the following completes the following statements?

Per 00303-C, Containment Entry, personnel inside containment _(1)_ required to immediately exit.

If the containment airlock inner door would NOT close when the personnel exited, the Tech Spec LCO 3.6.2, Containment Air Locks, Required Action would be to close the outer airlock door _(2)_.

(1)

A. are immediately B. are in no later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. are NOT immediately D. are NOT in no later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

57.

Initial conditions:

- Unit 1 is in a refueling outage.

- Core reload is in progress.

Current condition:

- The inner emergency air lock door is open and NOT capable of being closed.

Which one of the following completes the following statement?

Per Tech Spec 3.9.4, Containment Penetrations, the equipment hatch must be capable of being closed and held in place with a minimum of (1 ) bolts, and per Tech Spec 3.9.4, core reload (2) allowed to continue.

(1 )

A. 4 is B. 4 isNOT C. 8 is D. 8 isNOT

58.

Given the following:

- On-coming OATC is relieving the shift following 7 days off.

Which one of the following completes the following statement?

Per 10004-C, Shift Relief, the OATC is required to review, as a minimum, the narrative logs for the preceding _(1)_ days, and the OATC _(2)_ required to review all active Night Orders.

_(1 )_

A. 7 is B. 7 isNOT C. 3 is D. 3 i5NOT

59.

Given the following:

- Planned maintenance will cause multiple control room alarms.

- Expected alarms have been flagged.

Which one of the following completes the following statement?

Per NMP-OS-007-OO1, Conduct of Operations Standards and Expectations, for the expected alarms, subsequent recurring alarms associated with this same maintenance activity _(1 ) require a verbal announcement, and for the expected alarms, the associated ARP compensatory actions (2) required to be performed.

_(1 )_

A. do are B. do are NOT C. do NOT are D. do NOT are NOT

60.

Initial condition:

- Unit 1 is at 100% reactor power.

Current conditions:

- ALB1O-C05 RPI NON URGENT ALARM is received.

- DRPI Data A Failure LEDs are lit.

- General Warning LED for rod M12 is lit.

Which one of the following completes the following statement?

The purpose of the DRPI display console is to provide _(1)_ rod position indication, and based on the given conditions, the DRPI accuracy for rod M12 is (2)_ steps.

(1 )_ _(2)_

A. actual -10,+4 B. actual +10,-4 C. demanded -10,÷4 D. demanded +10,-4

61.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- Pressurizer Safety Valve A is declared inoperable due to a discrepancy found in previous test data.

Which one of the following completes the following statement?

Per Tech Spec LCO 3.4.10, Pressurizer Safety Valves, the required lift setting for the pressurizer safety valve is _(1)_ +/- 50 psig, and per Tech Spec LCO 3.4.10, the inoperable safety valve must be restored to OPERABLE status in no later than (2) or a unit shutdown will be required.

_(1 ) _(2)_

A. 2345 15 minutes B. 2345 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. 2460 15 minutes D. 2460 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

62.

Initial condition:

- Unit 2 reactor power is 12% with a shutdown in progress.

Current conditions:

- Intermediate Range N36 fails full-scale high.

- No operator action has been taken.

Which one of the following completes the following statement?

Based on the current conditions, an automatic reactor trip _(1) occur, and the P-6 SR HIGH FLUX TRIP block 2) require manual RESET when reactor power lowers below its associated reset setpoint.

_(1 )_ _(2)_

A. did will B. did will NOT C. did NOT will D. did NOT will NOT

63.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a SGTR on SG #3.

Current condition:

- 19030-C, Steam Generator Tube Rupture, is in progress.

Which one of the following completes the following statement?

Per 1 9030-C, the ruptured SG ARV lift setpoint is adjusted to (1 ),

and the reasons for this adjustment are to _(2).

A. (1) ll2Opsig (2) minimize radiation releases through the ARV and prevent lifting of MSSVs B. (1) 1120 psig (2) promote thermal stratification and prevent SG depressurization C. (1) ll6Opsig (2) minimize radiation releases through the ARV and prevent lifting of MSSVs D. (1) 1160 psig (2) promote thermal stratification and prevent SG depressurization

64.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- Containment entry is to be performed per 00303-C, Containment Entry.

Which one of the following completes the following statement?

Per 00303-C, the area inside the bioshield is posted as a _(1)_ Area, and per 00303-C, entry into the _(2)_ is prohibited.

(1 )_ _(2)_

A. Very High Radiation elevator B. Very High Radiation 261 foot mezzanine C. Locked High Radiation elevator D. Locked High Radiation 261 foot mezzanine

65.

Procedure titles as follows:

- 19000-C, Reactor Trip or Safety Injection

- 19100-C, Loss of All AC Power At time 1105:

- Unit 1 is in Mode 4.

- Multiple alarms are received on the QMCB and the QEAB.

Approximately 45 seconds later:

- Two of three white pot lights (left and center lights) are NOT lit on the QEAB for both 1 AAO2 and 1 BAO3.

- No operator action has been taken.

Which one of following completes the following statement?

Based on the current conditions, direct entry into 1) is required, and when performing the Immediate Operator Actions, the Reactor Trip Breaker status indication on the QMCB _(2)_ available.

_(1 ). _(2)_

A. 19000-C is B. 19000-C is NOT C. 19100-C is D. 19100-C is NOT

66.

Initial condition:

- Unit 1 is at 100% reactor power.

Current condition:

- The crew is implementing EOPs following a reactor trip.

Which one of the following completes the following statement?

Per 10020-C, EOP and AOP Rules of Usage, when performing steps in the EOPs, the crew _(1 )_ required to complete each step before continuing to the next step, and continuous action steps that are skipped by procedure step transitions _(2)_

required to be applied.

_(1 )_

A. is are B. is are NOT C. is NOT are D. is NOT are NOT

67.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a SGTR.

Current conditions:

- Crew is initiating the Foldout Page of 1 9000-C, Reactor Trip or Safety Injection.

- Containment pressure is 1 .4 psig.

- All SG NR levels are 8% and rising.

Per 10020-C, EOP and AOP Rules of Usage, which one of the following completes the following statements?

Based on the given conditions, the UO (1) allowed to take early operator action to isolate AFW to the ruptured SG.

Shift Supervisor permission _(2)_ required prior to performing early operator actions.

(1 ) _(2)_

A. is is B. is is NOT C. is NOT is D. is NOT is NOT

68.

Initial conditions:

- Unit 2 reactor trip and Si occurred due to a faulted SG.

- 19020-C, Faulted Steam Generator Isolation, is in progress.

Current conditions:

- UO reports an uncontrolled level rise on SG #1.

- Crew transitions to 19005-C, Rediagnosis.

- Crew is at the step to Check if this procedure should be implemented.

Which one of the following completes the following statement?

CSFST monitoring 1) suspended while performing 19005-C, and the required conditions for implementation of 19005-C _(2)_ met.

(1 )

A. is are B. is are NOT C. is NOT are D. is NOT are NOT

69.

At time 1200:

- Unit 1 reactor trip and SI occurred due to a LOCA.

At time 1230:

- RCS WR Tcold is 510°F and stable.

- 19012-C, Post-LOCA Cooldown and Depressurization, is in progress.

- Crew is at the step to Initiate RCS cooldown to cold shutdown.

Which one of the following completes the following statement?

Per 19012-C, the crew (1) allowed to lower RCS WR Tcold to 425 °F over the next 30 minutes, and the RCS cooldown rate is limited to reduce tensile stresses on the _(2) reactor vessel wall.

_(1 )_ _(2)_

A. is outer B. is inner C. is NOT outer D. is NOT inner

70.

Initial condition:

- Unit 1 reactor trip and SI occurred due to a LOCA.

Current condition:

- 19112-C, LOCA Outside Containment, is in progress.

Which one of the following completes the following statement?

Per 19112-C, to attempt to stop the leak the CCP discharge piping (1) be isolated, and the indication that will be used to determine when the inter-system LOCA has been isolated is (2)_.

(2)

A. will RCS WR pressure rising B. will Auxiliary Building rad monitors lowering C. will NOT RCS WR pressure rising D. will NOT Auxiliary Building rad monitors lowering

71 At time 1000:

- Unit 2 reactor tripped with a RED path on Heat Sink.

- 19231-C, Response to Loss of Secondary Heat Sink, is entered.

- Containment pressure is 1.8 psig.

- RCS pressure is 2290 psig.

- SGs #1 and #4 WR levels are 16%.

- SGs #2 and #3 WR levels are 37%.

- COP A is in service.

At time 1008:

- SGs #1 and #4 WR levels are 12%.

- SGs #2 and #3 WR levels are 31%.

- CETCs are 560 °F and slowly rising.

- MDAFW pump A has been returned to service.

Which one of the following completes the following statement?

Based on the given conditions, bleed and feed criteria (1) met, and when AFW flow is initially restored, feed flow rates _(2)_ limited to between 30 and 100 gpm to the selected SG.

(1 ). _(2).

A. are are B. are are NOT

0. are NOT are D. are NOT are NOT

72.

Initial conditions:

- Unit 1 reactor trip and SI occurred.

- 19121-C, Uncontrolled Depressurization of All Steam Generators, is in progress.

- SI is reset.

Current conditions:

- Crew is at the step to Check if RHR Pumps should be stopped.

- RAT lA de-energizes due to a fault.

- DG1A starts and re-energizes its associated bus.

- RCS pressure is 200 psig.

Which one of the following completes the following statement?

RHR pump A (1)_ required to be manually started, and the _(2)_ are required to be manually started.

_(1 )_

A. is Containment Coolers in high speed B. is Post-LOCA Cavity Purge Units C. is NOT Containment Coolers in high speed D. is NOT Post-LOCA Cavity Purge Units

73.

Initial conditions:

- Unit 1 reactor trip occurred.

- Both RATs de-energized due to a switchyard fire.

Current conditions:

- 19232-C, Response to Steam Generator Overpressure, is in progress.

- SG #2 pressure is 1250 psig.

- SG #2 NR level is 85%.

Which one of the following completes the following statements?

Per 19232-C, the UO is required to lower SG #2 pressure using _(1)_.

When SG NR level is greater than 92%, steam flow is NOT initiated because of the risk of (2).

.(1 ).

A. ARVs water hammer B. ARVs excessive steam dryer delta P C. steam dumps water hammer D. steam dumps excessive steam dryer delta P

74.

Initial conditions:

- Unit 1 is at 100% reactor power.

- Containment Spray pump A is tagged out.

Current conditions:

- Large break LOCA occurs.

- 19010-C, Loss of Reactor or Secondary Coolant, is in progress.

- Containment Spray pump B trips.

- Containment pressure is 22 psig.

- Containment hydrogen concentration is 5.1%.

Which one of the following completes the following statement?

The preferred method for reducing containment hydrogen concentration is _(1 )_ the containment atmosphere, and a(n) (2)_ path entry condition exists for 19251-C, Response to High Containment Pressure.

_(1 )_

A. diluting RED B. diluting ORANGE C. purging RED D. purging ORANGE

75.

Initial conditions:

- Unit 1 reactor trip and SI occurred due to a LOCA.

- Crew is evaluating CSFSTs.

Current conditions:

- Containment integrated dose is calculated to be Rads.

- 1 RE-002, Containment Low Range, is 800 mRlhour.

- 1 RE-003, Containment Low Range, is 875 mR/hour.

- Containment pressure is 3.5 psig.

Which one of the following completes the following statement?

Based on the given conditions, adverse EOP values _(1)_ required to be used, and per the major actions of 19253-C, Response to High Containment Radiation Level, the operators are required to verify (2)_ alignment.

(1 )

A. are CIA B. are CVI C. are NOT CIA D. are NOT CVI