Q1 — Reactor Trip Status Panel 000007EK2.03 (3.5)

Given:
• Unit 2 is at 60% Power.

The following sequence of events occurs:

• A Main Turbine trip occurs.
• OHA F-36, TURB TRIP & P-9, is illuminated.
• One of the Turbine Stop Valve Closed indicating lights on 2RP4 is flashing.

The flashing light on 2RP4 indicates that …

Q2 — PORV Discharge Temperature 000008AK2.02 (2.7)

Given:
• Unit 2 is in MODE 3.
• RCS Pressure is 2235 psig
• PZR Power Operated Relief Valve (PORV) 2PR1 is leaking.
• Pressurizer Relief Tank (PRT) pressure is 5 psig.
• PORV discharge temperature has stabilized at 230 °F.

Which ONE of the following will directly cause the indicated PORV discharge temperature to LOWER?

Q3 — SBLOCA Subcooling / Steam Tables 000009EK1.02 (3.5)

Given:
• Unit 2 has experienced a Small Break LOCA with a Loss of Off-Site Power.
• A fault developed on the 2A 4KV Bus and the Bus is de-energized.
• All available ECCS Pumps are currently running.
• Containment Pressure is currently 4.3 psig.
• RCS Pressure is currently 1035 psig.
• The crew has transitioned to 2-EOP-LOCA-2, Post LOCA Cooldown and Depressurization.
• The crew is implementing "Charging Pump Reduction" major action of EOP-LOCA-2.
• Based on operability concerns with the Subcooling Margin Monitor, the CRS has directed the RO to determine subcooling requirements using Steam Tables.

Which ONE of the following choices is the MAXIMUM RCS (Core Exit) temperature that will allow stopping one Charging Pump in accordance with step 21 of 2-EOP-LOCA-2?

[REFERENCES PROVIDED]

Q4 — RCP Motor Winding Temperature 000015AK3.01 (2.5)

Given:

Which ONE of the following would be an indication of the potential for damage to a Reactor Coolant Pump and require tripping the Reactor Coolant Pump in accordance with S2.OP-AB.RCP-0001, Reactor Coolant Pump Abnormality, Attachment 2, Stopping Reactor Coolant Pumps.

Q5 — Excess Letdown / SI Isolation 000022AA1.07 (2.8)

Given:
• Unit 2 is at 100% Power.
• Normal Letdown has been isolated due to a problem with the Letdown Pressure Control Valve, 2CV18.
• Excess Letdown has been established to the VCT in accordance with S2.OP-SO.CVC-0003, Excess Letdown Flow.

Immediately following a Safety Injection (SI) signal, Excess Letdown will __(1)__.

Note: 2CV278, Excess Letdown Isolation Valve
   2CV131, Excess Letdown Isolation Valve
   2CV284, Seal Return Isolation Valve
   2CV116, Seal Return Isolation Valve

Q6 — Shutdown LOCA 000025AA2.04 (3.3)

Given:
• 21 RHR Pump is in service aligned for Shutdown Cooling.
• RCS Temperature is 325 °F.
• RCS Pressure is 300 psig and lowering.
• PZR Level is 10% and lowering rapidly.
• Containment Pressure is 0.1 psig.
• 2R41D, Plant Vent, radiation monitor is rising.

Which ONE of the following identifies the required procedure and action to mitigate this event?

Q7 — PZR PORV Fails Open 000027AK3.03 (3.7)

Given:
• Unit 2 is at 100% Power.
• 2PR1, Pressurizer PORV, fails opens while in Automatic and cannot be closed in Manual from the control console in accordance with S2.OP-AB.PZR-0001, Pressurizer Pressure Malfunction.

In accordance with S2.OP-AB.PZR-0001, which ONE of the following identifies the NEXT required action, and if pressure continues to lower, what subsequent action is taken and why?

Q8 — ATWS Turbine Trip 000029EK3.12 (4.4)

Given:
• Unit 2 was at 100% Power when a trip of both Steam Generator Feed Pumps occurred.

The following sequence of events occurs:

• ALL SG NR LO-LO level setpoints are reached, but the reactor failed to trip.
• ALL attempts to trip the reactor from the control room were unsuccessful and the reactor trip is NOT confirmed.
• The crew enters 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

Complete the following statements:

In accordance with 2-EOP-TRIP-1, which one of the following is the NEXT required action and why?

Q9 — MSLB Containment Cooling 000040G2.4.46 (4.2)

Given:
• A design bases Main Steam Line Break coincident with a Loss of Off-Site Power has occurred on Unit 2.

The PO reviewing the OHAs and Control Console Bezel Alarms recognizes and announces the following event relevant alarms:

• J-3, 2C 4KV VTL BUS DIFF PROT
• C-6, CNTMT PRESS HI-HI
• C-5, 21 CFCU WTRFLO TRBL
• BEZEL 1-2, 21 CFCU AIR FLOW LO

The PO verifies 21SW58 (21 CFCU Inlet) and 21SW72 (21 CFCU Outlet) service water valves are OPEN.

Which ONE of the following completes the statements below?

Containment cooling design bases configuration __(1)__ met. This is because ____(2)___.

Q10 — Loss of MFW / Dry SG Feed Restriction 000054AK1.02 (3.6)

Given:
• Unit 2 was at 100% Power when a Loss of all Main Feedwater occurred.
• Operators have not been able to initiate Auxiliary Feedwater (AFW) and have transitioned to 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink.
• Bleed and Feed has been initiated.
• Core Exit Temperatures (CETs) are now LOWERING.
• All SG Wide Range (WR) Levels are 7 % and stable.

Subsequently, feed flow capability has just been restored and the crew has returned to the major action step for "SECONDARY HEAT SINK RESTORATION".

Based on the above conditions and In accordance with 2-EOP-FRHS-1, complete the statement below concerning the limitation when restoring feed flow and why?

Feed one SG…

Q11 — EDG Loading Limits for PZR Heaters 000056G2.1.25 (3.9)

Given:

• Unit 2 was at 100% Power when a Loss of Off-Site Power occurred.
• Operators have transitioned to 2-EOP-TRIP-2, Reactor Trip Response.
• All Emergency Diesel Generators are loaded onto their respective 4KV Vital Buses.

The CRS has directed you to energize the 21 PZR Backup Heaters from the 2C Vital Bus in accordance with the station operating procedure.

A procedural caution states the following; "Aligning pressurizer heaters to vital bus adds approximately 210 KW to bus load".

The 2C diesel is currently loaded to the 2000 hour limit. In order to add the PZR heater load of 210 KW and NOT exceed the 2000 hour limit, the current 2C diesel loading must be adjusted to no greater than ______.

Q12 — Loss of VIB VCT Level and Overpressure Protection 000057AA2.13 (3.0)

Given:

• Unit 2 was at 100% Power when a Loss of the 2A 115V Vital Instrument Bus occurred.
• The CRS has entered S2.OP-AB.115-0001, Loss of 2A Vital Instrument Bus.

The following Volume Control Tank (VCT) components and indications have been affected:

• LT-112, VCT Level - Loss of indication and alarms.
• PI-139, VCT Pressure - Loss of indication.
• The VCT makeup system will be unavailable for normal makeup.

The crew has restored normal letdown in accordance with the procedure and has selected 2CV35 to MANUAL FLOW TO VCT.

Complete the following statements:

The 2LT-114 VCT level can be monitored in the control room using the _(1)_. If VCT level continues to rise above 77%, over-pressurization protection of the VCT is provided by _(2)_.

Q13 — Loss of 2A 125 VDC Bus Equipment Impact 000058AA2.03 (3.5)

Given:
• Unit 2 is at 100% Reactor Power

At time 16:00
• OHA B-2, "2A 125 VDC CNTRL BUS VOLT LO" actuates
• 2A Vital 125 VDC Bus voltage is reading 0 VDC on 2RP9

Considering ONLY the following equipment malfunctions below:

1. #1 SGFP Emergency Oil Pump loses power
2. Main Turbine Emergency Oil Pump loses power
3. 2A EDG is NOT available for start

Which ONE of the following completes the statement below?

With a confirmed 2A Vital 125 VDC Bus voltage of 0 VDC, Unit 2 will experience equipment malfunction(s) ______.

Q14 — Service Water Bay Leak and Tech Spec 000062G2.2.40 (3.4)

Given:

• Unit 2 is at 100% Power.
• 24 Service Water Pump is Cleared & Tagged for a silt inspection.
• 21, 25, and 26 Service Water Pumps are in service.
• 23 Service Water Pump is in AUTO.

The following OHA alarms are received:

• B-13, 21 SW HDR PRESS LO
• B-14, 22 SW HDR PRESS LO
• B-29, 21-23 SW PUMP SMP AREA LVL HI

Which Abnormal Operating Procedure will isolate the identified service water leak, and once the leak is isolated, what Technical Specification LCO is applicable?

Q15 — Loss of Control Air ECAC Actions 000065AA1.04 (3.5)

Given:

• Unit 2 is at 100% Power.
• The crew recognizes degrading Control Air Header pressures.
• The CRS enters S2.OP-AB.CA-0001, Loss of Control Air.
• 2A Control Air Header pressure is 93 psig.
• 2B Control Air Header pressure is 88 psig.

Note: ECAC = Emergency Control Air Compressor

In accordance with S2.OP-AB.CA-0001, what action is required, and if control air (CA) header pressure continues to LOWER, what subsequent action will be required?

Q16 — LOCA Outside Containment Indication WE04EK2.1 (3.5)

Given:
• Unit 2 has experienced a LOCA.
• RCS Pressure is 1300 psig.
• Total ECCS Injection Flow is 400 gpm.
• The CRS has transitioned from 2-EOP-TRIP-1, Reactor Trip or Safety Injection, to 2-EOP-LOCA-6, LOCA Outside Containment.

In accordance with 2-EOP-LOCA-6, what indication is specifically checked to ensure successful leak isolation and allow exit from the procedure?

Q17 — Loss of Emergency Recirculation Mitigation Strategies WE11EK1.2 (3.6)

Given:
• Unit 2 has experienced a design bases Large Break LOCA coincident with a Loss of Off-Site Power.
• 2B Emergency Diesel Generator tripped.
• 21 RHR Pump tripped.
• The CRS has transitioned to 2-EOP-LOCA-5, Loss of Emergency Recirculation.

In accordance with 2-EOP-LOCA-5, which of the following mitigation strategies are applicable based on CURRENT plant conditions and will NEED to be implemented?

1. Run All CFCUs in High Speed.
2. Minimize SI Flow to minimum for adequate decay heat removal.
3. Depressurize the RCS to minimize RCS subcooling.
4. Make up to the RWST.

Q18 — FRHS-1 RCS Pressure vs SG Pressure Check WE05EA2.1 (3.4)

Given:
• Unit 2 has experienced a Reactor Trip from 100% Power.
• Safety Injection has immediately actuated on low RCS Pressure.
• ALL Auxiliary Feed Pumps have been lost and can't be recovered.
• The CRS has transitioned to 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink at step 20 of 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

2-EOP-FRHS-1 Step 3 (Step 1 in current EOP rev) asks; "IS RCS PRESSURE GREATER THAN ANY INTACT OR RUPTURED SG PRESSURE?"

Which ONE of the following actions is required if the operator answers NO and why?

Q19 — Dropped Rod Step Counter Reset APE03AK3.04 (3.8)

Given:
• Unit 2 reactor power was reduced to 74% Power.
• A dropped Control Bank D Group 1 rod is being recovered in accordance with S2.OP-AB.ROD-0002, Dropped Rod.

Shortly before the crew starts withdrawing the dropped rod, S2.OP-AB.ROD-0002 directs the crew to reset the control bank D group 1 step counter to zero.

Why does the affected group step counter need to be reset to zero?

Q20 — Misaligned Rods Required Action APE05AA1.04 (3.9)

Given:
• Unit 2 was initially at 100% Power.

Subsequently, the following sequence of events occurs:

• Automatic Turbine runback occurs due to an issue with the stator water cooling system.
• During the load reduction, the RO reports that two (2) Control Bank D rods have stopped moving at 215 steps.
• The CRS enters S2.OP-AB.ROD-0001, Immovable / Misaligned Control Rods.
• The RO has placed the Rod Bank Selector Switch in MANUAL.
• Control Bank D Group Demand counters are presently at 185 steps.
• The runback terminates with reactor power at 80 %.
• Tavg is being maintained within +/- 1.5 °F of program.

In accordance with S2.OP-AB.ROD-0001, and assuming the two control rods will not be restored to operable status, which ONE of the following describes a required action that the crew will take.

Q21 — Rapid Boration per EOP-TRIP-2 000024AK2.03 (2.7)

Given:
• Following a Unit 2 Reactor Trip, the crew has transitioned to 2-EOP-TRIP-2, Reactor Trip Response.
• The crew is performing the Control Rod Insertion Step.
• Two Control Rods have failed to fully insert.
• 2CV175, RAPID BORATE STOP VALVE will NOT open.

Which of the following describes the valve manipulations required in accordance with 2-EOP-TRIP-2, Reactor Trip Response, to establish rapid boration.

Q22 — IR Channel Bypass Alarm APE33AA2.09 (3.4)

Given:
• Unit 2 is at 100% Power.
• The Intermediate Range (IR) Channel N35 has just failed high.
• The crew has entered S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunction.
• The PO is removing N35 from service in accordance with S2.OP-SO.RPS-0001(Q), Nuclear Instrumentation Channel Trip / Restoration and OHA E-29, SR & IR TRIP BYP, annunciates.

Which of the following identifies the cause of the alarm?

Q23 — Area Rad Monitor Crane Interlock APE61AK3.02 (3.4)

Which of the following interlocks are activated when Area Radiation Monitor 2R32A, Fuel Handling Crane fails to its' alarm setpoint?

Q24 — Core Cooling Red Path Validation EPE74G2.1.19 (3.9)

Given:
• Unit 2 has experienced a LOCA.
• The crew is implementing the Critical Function Status Trees.
• The RO has identified that the SPDS Overview Screen indicates a Red Path for Core Cooling.
• RCS Subcooling is < 0 °F.
• No RCPs are running.

Which ONE of the following RCS Parameters would validate a Core Cooling Red Path?

Q25 — LOCA Outside Containment from TRIP-3 WE02G2.4.45 (4.1)

Given
• Unit 2 has experienced a Small Break LOCA.
• The CRS has transitioned to 2-EOP-TRIP-3, SI Termination.
• 21 Charging Pump has been stopped and a normal charging alignment has been established.
• 21 and 22 Safety Injection Pumps have been stopped.
• 21 and 22 RHR Pumps have been stopped.

Prior to attempting to establish normal letdown, a number of overhead annunciators alarm and or reflash. The RO reports the following indications and OHA annunciators:

• A-6, RMS HI RAD OR TRBL, due to 2R41D, Plant Vent Effluent
• A-41, AUX ALM SYS PRINTER, due to 23 and 24 RHR Sump Pump starts.
• C-34 22 RHR SUMP OVRFLO
• D-40, SUBCLG CH A MARGIN LO, due to subcooling at 9 °F
• D-48, SUBCLG CH B MARGIN LO, due to subcooling at 9 °F
• E-36 PZR HTR OFF LVL LO, due to Pressurizer Level off scale low and unable to be recovered.

What procedure will be used to mitigate this event?

Q26 — SMM Adverse Containment WE16EK2.1 (3.0)

Given:
Unit 2 has experienced a LOCA.

At T+0:
• Containment Pressure has peaked at 10 psig.
• 2R44A, Containment High Range Monitor is reading 5E05 R/HR.
• 2R44B, Containment High Range Monitor is reading 7E05 R/HR.

At T+3 hours:
• Containment Pressure is currently reading 2.5 psig.
• 2R44A, Containment High Range Monitor is reading 2E04 R/HR.
• 2R44B, Containment High Range Monitor is reading 1E04 R/HR.

Complete the following statements concerning operation of the Subcooling Margin Monitor (SMM):

At T+0 the SMM is operating in _(1)_ Mode, and at T+3 hours the SMM will _(2)_ reset to Normal Mode.

Q27 — LOCA Voiding Indication WE03EK1.3 (3.5)

Given:
• Unit 2 has experienced a Small Break LOCA.
• An automatic Reactor Trip and SI have occurred.
• All RCPs have been stopped.
• The crew has transitioned to 2-EOP-LOCA-2, Post LOCA Cooldown and Depressurization.

In accordance with 2-EOP-LOCA-2, which ONE of the following operational indications describes how voiding can be identified in the RCS?

Q28 — RCP Standpipe Level Hi 003000A1.10 (2.5)

Given:
• Unit 2 is at 100% Power.
• Control Console Bezel Alarm for 21 RCP "STANDPIPE LEVEL HI" annunciates.
• The RO reports 21 RCP Seal Leak-off Flow recorder indication has LOWERED.

The "STANDPIPE LEVEL HI" alarm is an indication of excessive leakage from the RCP _(1)_.

Q29 — Charging Pump Power Supplies 004000K2.03 (3.3)

Given:
• Unit 2 is at 100% Power
• 2C Bus Differential Protection relay actuates and results in the 2C 4KV Bus de-energized.

Which ONE of the following lists the available Charging Pumps following the loss of the 2C 4KV Vital Bus?

Q30 — CVCS CV71 Post-SI 004000G2.1.28 (4.1)

Given:
• A Unit 2 Pressurizer Safety Valve has failed open.
• A Reactor Trip and Safety Injection (SI) have automatically actuated.

The Reactor Operator is throttling closed on 2CV71, Seal Pressure Control Valve.

What is the effect on Charging Pump discharge pressure and charging flow to the RCS?

Charging Pump discharge pressure will...

Q31 — RHR HX Cooldown Rate Control 005000K6.03 (2.5)

Given:

• Unit 2 is in MODE 5.
• 21 RHR HX Loop is providing Shutdown Cooling with a cooldown rate of 20 °F/hr.
• 21RH18, RHR HX Flow Control Valve, is throttled at 40 % to maintain total flow at 2500 gpm.
• 2RH20, RHR HX Bypass Valve, is throttled at 30 % open.

Subsequently the following occurs:

• Foreign material dropped in the Refueling Cavity is introduced into the RHR system causing partial blockage on the 21 RHR HX tubes.
• Cooldown rate has lowered to 5 °F/hr.

Based on the above conditions, in order to maintain a 20 °F/hr cooldown rate, the operator will be required to _______. (Assume decay heat load remains constant)

Q32 — EOP-FRTS-1 PTS Mitigation Basis 006000K5.04 (2.9)

Given:

The Unit 2 crew has entered 2-EOP-FRTS-1, Response to Imminent Pressurized Thermal Shock.

The procedure directs various mitigating actions including termination of SI and the starting of an RCP. What are the basis for these two mitigating actions?

Q33 — Containment TS Pressure and Temperature Limits 007000K3.01 (3.3)

Given:

• Unit 2 is at 100% Power.
• Containment pressure is 0 psig.
• Containment temperature is 99 °F.

Subsequently, the following sequence of events occurs:

• A load rejection results in a reactor trip.
• Following the trip, a Pressurizer Safety Valve opens, and does not completely reseat.
• The PRT rupture disk has relieved to the containment.
• Containment pressure is rising at 0.1 psig every 5 minutes.
• Containment temperature is rising at 1 °F every 5 minutes.

Assuming containment pressure and temperature trends remain constant, which ONE of the following Containment Technical Specification LCO(s), if any, will NOT BE MET ONE HOUR from now?

Q34 — CCW Thermal Barrier Leak Indications 008000K1.04 (3.3)

Given:

• Unit 2 is at 100% Power.

The RO reports the following console alarms on 2CC1:

• CC HDR ACTIVITY HI.
• SURGE TANK LEVEL HI-LO.
• DISCHARGE FLOW LO.

The crew has entered S2.OP-AB.CC-0001, Component Cooling Abnormality. Based on just the above plant conditions, which ONE of the following is the source of leakage into the Component Cooling System?

Q35 — CCW Pump Status After SEC Mode 3 Loading 008000K4.09 (2.7)

Given:

• Unit 2 is at 100% power.
• 21 and 22 CCW Pumps are running.
• 23 CCW Pump is in AUTO.

Subsequently;

• The Unit experiences a valid Safety Injection actuation coincident with a Loss of Off-Site Power.

Which of the following describes the status of the CCW Pumps following successful SEC loading?

Q36 — PZR Pressure Channel Fails Low 010000A3.02 (3.6)

Given:
• Unit 2 is in MODE 3.
• Pressurizer (PZR) Pressure is 2235 psig.
• RCS Temperature is 547 °F.
• PZR Pressure Channel I (2PT-455) is selected for Control.
• PZR Pressure Channel II (2PT-456) is selected for Alarm.

If PZR Pressure Channel I fails LOW and with NO operator action, PZR pressure will rise until ______.

Q37 — OT Delta-T Inputs 012000K5.01 (3.3)

Which ONE of the following lists the correct operational plant parameters used as input to the OTΔT reactor protection setpoint calculation?

Q38 — Loss of Tripping Capability RTB 012000G2.4.31 (4.2)

Given:
• Unit 2 is at 100% Power
• Control Console Bezel Alarm "LOSS OF TRIPPING CAPABILITY" is received for Reactor Trip Breaker (RTB) "A"

Which ONE of the following describes the effect on Reactor Trip Breaker (RTB) "A" from this alarm condition?

Q39 — ESFAS SI Block / Containment High Pressure 013000K4.12 (3.7)

Given:
• Unit 2 is in MODE 3.
• The crew is implementing S2.OP-IO.ZZ-0006, Hot Standby to Cold Shutdown.
• The crew has commenced a cooldown and depressurization to Cold Shutdown to comply with a Technical Specification action requirement.
• RCS Temperature is 535°F
• RCS Pressure is 1890 psig
• All actions for current plant conditions have been completed in accordance with S2.OP-IO.ZZ-0006.

Multiple failures have just occurred resulting in rapid depressurization of ALL Steam Generators (SGs) INSIDE containment causing a Safety Injection actuation.

Which of the following ESFAS initiation signals and logic caused the Safety Injection actuation to occur?

Q40 — CFCU Containment Temperature Rise 022000A1.01 (3.6)

Given:
• Unit 2 is at 100 % Power.
• Four (4) CFCUs are in service in HIGH speed.
• Containment temperature is 95 °F.
• Containment pressure is 0.10 psig.

Consider the below conditions and its impact to Containment Fan Coil Unit performance during normal plant operation.

Which of the following conditions could result in a RISE in containment temperature?

1. Running CFCUs in LOW speed.
2. Starting additional Service Water Pumps.
3. Increase in service water temperature.
4. Erosion of the flow orifice upstream of the SW223.

Q41 — ECCS Semi-Automatic Switchover 026000K4.08 (4.1)

Given:
- Unit 2 has experienced a Reactor Trip and Safety Injection due to a Large Break LOCA.
- RWST Level has lowered to less than 15.2 feet on 2/4 RWST Level Channels.

With NO operator action, which choice describes AUTOMATIC actions that will occur based on the above RWST Level?

Q42 — EOP-LOCA-5 Table C CS Pumps Required 026000G2.1.25 (3.9)

Given:
- Unit 2 has experienced a design bases Large Break LOCA.
- The 2A Vital Bus is de-energized due to a Differential Protection Fault on the bus.
- The 22 RHR Pump has tripped.

At T+0:
- The crew enters 2-EOP-LOCA-5, Loss of Emergency Recirculation
- RO reports RWST Level is 20 feet.

At T+6 minutes:
- The crew is performing Step 9 of EOP-LOCA-5 to determine the required number of Containment Spray Pumps using Table C.
- RO reports Containment pressure is 18 psig.

At T+6 minutes, determine the relative RWST Level and the number of Containment Spray Pumps required in accordance with EOP-LOCA-5, Table C?

[REFERENCES PROVIDED]

Q43 — MS10 Atmospheric Relief Valve Flow and AB.STM-0001 039000K1.02 (3.3)

Given:
- Unit 2 is at 100% Power when the 21MS10, 21 SG Atmospheric Relief Valve, fails open.
- The operator is unable to close the valve using the control console valve controller.
- The crew enters S2.OP-AB.STM-0001, Excessive Steam Flow.

Complete the following statements:

1) The rated design flow through the 21MS10 is _(1)_ steam flow.
2) After performing the actions of the Continuous Action Statement of S2.OP-AB.STM-0001 to trip the reactor and initiate a Main Steam Line Isolation, a Safety Injection (SI) _(2)_ required.

Q44 — AFW Pump Auto Start on Both SGFP Trip 059000K1.02 (3.4)

Given:
- Unit 2 is performing a Technical Specifications required shutdown in accordance with S2.OP-IO.ZZ-0004, Power Operation.
- 22 SGFP has been removed from service in accordance with S2.OP-SO.CN-0002, Steam Generator Feed Pump Operation.
- Reactor Power is now 24% and the 21 SGFP has just tripped.

With NO operator action, what will be the status of the Auxiliary Feed Pumps?

Q45 — Loss of Control Air BF19 Closure 059000A2.12 (3.1)

Given:
- Unit 2 is at 100% Reactor Power.
- A complete loss of ALL Station Air has occurred.
- The crew has entered S2.OP-AB.CA-0001, Loss of Control Air.
- BOTH Control Air Header Pressures are 95 psig and LOWERING.

What is the expected impact, if any, to the Main Feedwater Regulating Valves (21-24BF19) and what action will the crew take, if control air pressure continues to lower, in accordance with S2.OP-AB.CA-0001?

Q46 — AFW Pressure Override / SG Levels 061000A3.03 (3.9)

Given:

• Unit 2 is at 100% Reactor Power.
• The Unit experiences a Reactor Trip coincident with a Loss of Off-Site Power.
• 21 AFW Pump PRESSURE OVERRIDE console bezel is illuminated and the associated AF21's remain closed.

With NO operator action, which ONE of the following indications will exist regarding SG level control?

Q47 — 4KV Degraded Voltage / SEC Mode 062000K1.02 (4.1)

Given:

• Unit 2 is responding to a valid Safety Injection (SI) signal.
• Safety Injection has been RESET.
• ALL SECs have been RESET.
• ALL EDGs are running unloaded.
• 4KV Buses 2A and 2C are aligned to 23 Station Power Transformer (SPT).
• 4KV Bus 2B is aligned to 24 SPT.

Subsequently, 24 SPT experiences a failure causing its secondary voltage to drop and stabilize at 3600 volts.

Complete the following statement concerning the effect of this failure on the 2B 4KV Vital Bus:

The 2B 4KV Vital Bus will...

Q48 — EDG KVAR Loading / Voltage Control 062000A4.07 (3.1)

Given:

• Unit 2 is at 100% Power.
• The 2A EDG is paralleled to the 2A 4KV Bus for Surveillance Testing in accordance with S2.OP-ST.DG-0001, 2A Diesel Generator Surveillance Test.
• Reactive load is 1200 KVAR OUT.

In accordance with S2.OP-ST.DG-0001, what action is needed to RAISE reactive load to 1400-1500 KVAR OUT?

Q49 — 125VDC Battery Discharge Indication 063000A4.03 (3.0)

Given:

• The Unit 2 125 VDC Vital Bus Batteries are aligned to "float charge" mode.
• A Loss of All AC Power event has occurred.

What 125 VDC Battery indications in the control room will indicate that the batteries are discharging? How many hours of operation by design are the batteries sized for after a loss of all AC power?

Q50 — EDG Starting Air Receiver Capability 064000K6.07 (2.7)

Given:

• The Unit 2 is at 100% Power.
• 2A Emergency Diesel Generator (EDG) Starting Air Receiver 21A is isolated and cleared tagged for maintenance.
• A Loss of Off-Site Power has just occurred.

Complete the following statement regarding the 2A Emergency Diesel Generator (EDG) starting air system capability and response.

Following an SEC start signal, the 2A EDG __(1)__ start and achieve rated speed of 900 RPM in ≤ 13 seconds. The 21B starting air receiver is aligned to supply __(2)__ air start motors.

Q51 — SGBD Rad Monitor Warning Setpoint 073000K4.01 (4.0)

Which ONE of the following describes the AUTOMATIC actuations, if any, that will occur if a R19, Steam Generator Blowdown Radiation Monitor reaches its WARNING setpoint?

Q52 — SW Nuclear Header Leak EDG/CFCU Supply 076000K3.07 (3.7)

Given:

• Unit 2 is at 100% power.
• The crew is implementing S2.OP-AB.SW-0001, Loss of Service Water Header Pressure.
• The problem has been identified as a large Service Water leak in the Auxiliary Building just downstream of the 21SW22, Nuclear Header Inlet Valve.
• 21SW22 has been closed to isolate the leak.
• 21SW23 and 22SW23 (Header tie valves) remain closed.

Given the above conditions, which of the following describes Service Water Cooling supplies to the Emergency Diesel Generators (EDGs) and the Containment Fan Coil Units (CFCUs) if a Design Basis LOCA was to occur?

Q53 — SW Pump Trip / 1A 4KV Bus Differential 076000A2.01 (3.5)

Given:

Initial Conditions:
• Unit 1 is at 100% Power.
• #3 Service Water Bay is cleared and tagged (isolated) due to a leak on the 15SW3, 15 SW Pump Discharge Valve.
• The 1A EDG is running paralleled to the bus for a normally scheduled monthly surveillance.
• 11 and 13 SW Pumps are in service.
• 12 SW Pump is in AUTO.

Current Conditions:
• 13 SW Pump trips
• One minute later the 1A EDG output breaker opens due to 1A 4KV Vital Bus Differential.

Which ONE of the following describes the required mitigating actions for the event?

Q54 — Emergency Control Air Compressor Power Supply 078000K2.02 (3.3)

Given:

• Unit 1 is at 100% Power.
• The #1 Emergency Control Air Compressor (ECAC) is running for testing in accordance with S1.OP-PT.CA-0001, Emergency Control Air Compressor Test.

Which ONE of the following would result in the loss of the #1 ECAC?

Q55 — Phase A Containment Isolation Valves 103000A3.01 (3.9)

Given:

• Unit 1 Operators are responding to a Reactor Trip and Safety Injection.
• The crew is verifying valves in their Safeguards positions in accordance with 1-EOP-TRIP-1, Reactor Trip or Safety Injection.

Which of the following valves receive a Phase A Isolation signal to close?

Q56 — Rod Drive MG Set Power Supplies 001000K2.05 (3.1)

Given:
• Unit 1 is operating at 100% Power.
• The 1E 460 volt bus is de-energized following a trip of its feeder breaker.
• Tagging is in progress to allow troubleshooting of 1E 460 volt bus.

The operator mistakenly opens the 1F 460 volt bus feeder breaker, de-energizing the 1F 460 volt bus.

What is the consequence, if any, of this action?

Q57 — PZR Level Channel I Fails High 016000K3.02 (3.4)

Given:
• Unit 1 is operating at 100% Power.
• All systems are operating in AUTO.
• PZR Level Control System selected to Channel I for Control.
• PZR Level Control System selected to Channel II for Alarm.

A failure causes the following sequential plant events. Assume NO operator actions are taken.

• Charging Flow reduces to minimum.
• Actual PZR level drops slowly.
• Letdown isolates and PZR heaters turn off.
• A Reactor Trip eventually occurs on high PZR level.

Which ONE of the following failures would cause the above sequential events?

Q58 — Subcooling Margin Monitor Inputs 017000K4.01 (3.4)

Which ONE of the following lists the parameters used by the Subcooling Margin Monitor to calculate subcooling margin?

Q59 — Containment Ventilation Isolation 029000K1.03 (3.6)

1. MANUALLY initiating which of the following from the Control Room Console will also result in a Containment Ventilation Isolation signal?

2. Which valves receive a closed demand from the Containment Ventilation Isolation signal?

Q60 — ADFCS SG Level Channel Failure 035000K6.03 (2.6)

Given:
• Unit 2 is at 100% Power.
• Steam Generator level control and SGFPs are in AUTO.
• 21 Steam Generator NR Level Channel I failed high due to a sensor malfunction.
• No corrective actions have been initiated yet.

Complete the following statement concerning the response of the feedwater control system if 21 Steam Generator NR Level Channel II fails LOW?

The Ovation Advanced Digital Feedwater System will initiate OHA G-7, ADFCS ALTERNATE ACTION, and ....

Q61 — Steam Dump PT-507 Fails High 041000K3.05 (2.9)

Given:

• Unit 2 is operating at 100% Power.
• The Steam Dumps are in Main Steam Pressure Control Mode - AUTO due to a previous failure of 2PT-506, Main Turbine Steam Line Inlet Pressure Channel II.

A Reactor Trip and a malfunction causing 2PT-507, Main Steam Header Pressure, to fail high have just occurred.

With 2PT-507 failed HIGH, which ONE of the following describes how the Steam Dump System and the plant will respond, assuming no operator action is taken?

Q62 — SFP Anti-Siphon Design 033000K4.03 (2.6)

Design features of the Spent Fuel Cooling and Purification System ensure the fuel stored in the Spent Fuel Pool will not become uncovered as a result of any postulated loss of system integrity.

Complete the following statement that best describes this design feature.

The Spent Fuel Pool is designed with…

Q63 — Condenser Air Removal AR25 Stuck Open 055000K3.01 (2.5)

Given:

• Unit 2 is at 100% Power.
• The Plant Operator (PO) is swapping Condenser Vacuum Pumps in accordance with S2.OP-SO.AR-0001, Condenser Air Removal System Operation.
• The PO has started 24 Vacuum Pump successfully and has just initiated a stop on 22 Vacuum Pump.
• The 22AR25, Air Ejector Suction Isolation Valve, remains OPEN.

Which ONE of the following describes the status of main condenser vacuum and what procedural action the crew will take to mitigate the event?

Q64 — CW Malfunction / Rapid Load Reduction [OUTDATED] 075000K2.02 (2.5)

Given:

• Unit 2 are at 100% Power.
• 21A Circulator is out of service (C/T) for Waterbox cleaning.
• 23B Circulator is out of service (C/T) for Traveling Screen replacement.
• A Liquid Waste release is in progress from 21 CVCS Monitor Tank to the 21 SW Header.

The following sequence of events occurs:

• 21B Circulator trips.
• The crew enters S2.OP-AB.CW-0001, Circulating Water System Malfunction.
• Field operator makes an error in throttling hotwell isolation valves resulting in 21A and 21B Hotwell levels at 30 inches.
• 21 Condensate Pump amps are oscillating.

Based on the above conditions, which one of the following describes the next required actions and the MAXIMUM power level allowed in accordance with station procedures?

Note: S2.OP-AB.CN-0001, Main Feedwater / Condensate System Abnormality
         S2.OP-AB.LOAD-0001, Rapid Load Reduction

Q65 — Fire Pump Start on Loss of AC 086000A1.05 (2.9)

Given:

• Unit 2 is at 100% Power.

The following sequence of events occurs:

• OHA A-15, FIRE PMP 1/2 RUN in alarm
• OHA A-23, FIRE PUMP 1/2 TRBL in alarm.
• BOTH Fire Pumps are running.
• NO other Fire Protection System alarms are present.
• Fire protection reports NO fire system actuations.
• Fire main header pressure is 135 psig and stable.

Which ONE of the following describes the cause for the above conditions?

Q66 — Operator Burdens / Annunciator Marking G2.1.1 (3.8)

During shift turnover, the on-coming RO notices an OHA window with reflash capability (multiple inputs) with a single strand of red tape diagonally across the annunciator window.

In accordance with OP-AA-102-103-1001, Operator Burdens Program, which ONE of the following describes the status of the annunciator window?

Q67 — Shift Turnover Pre/Post Relief Actions G2.1.3 (3.7)

Which ONE of the following describes Reactor Operator pre and post-shift relief actions that should be implemented by the oncoming operator in accordance with OP-AA-112-101, Shift Turnover and Relief?

Q68 — Control Rod Movement Requirements G2.1.37 (4.3)

During non-transient conditions, what is the MINIMUM information that the reactor operator shall state just prior to manually manipulating control rods in accordance with OP-AP-300-1001, PWR Control Rod Movement Requirements?

Q69 — Component Configuration Control / TSAS Positioning G2.2.14 (3.9)

A one (1) hour or less Technical Specification Action Statement (TSAS) requires a component to be positioned to the CLOSED position.

In accordance with OP-AA-108-101-1002, Component Configuration Control, the component will be positioned by _(1)_ and then the INDEPENDENT VERIFICATION (IV) will be performed _(2)_.

Q70 — Breaker Tagging / Removal from Energized Bus G2.2.13 (4.1)

Given:
• Unit 2 is in MODE 5 during a scheduled maintenance outage.
• A Red Blocking Tag (RBT) is hung on a 460V breaker racking mechanism.
• The 460V Bus associated with the breaker is energized.
• The breaker is tagged in the "Disconnect" (DI) position.

Which ONE of the following describes the required tagging sequence when removing the breaker from its cubicle to facilitate maintenance?

[REFERENCE PROVIDED]

Q71 — Surveillance Dollar Sign ($) Significance G2.2.12 Knowledge of surveillance procedures (3.7)

When performing a Surveillance procedure, the operator encounters a step which has a dollar sign ( $ ) under the line where the operator initials completion of that step.

What is the significance of the dollar sign ( $ )?

Q72 — Radwaste Release RP Support Requirement G2.3.14 Knowledge of radiation/contamination hazards (3.4)

Which ONE of the following evolutions performed by Operations Department personnel, in accordance with station procedures, will require Radiation Protection support due to potential radiation/contamination hazards?

Q73 — Emergency Dose Extension at ALERT G2.3.4 Knowledge of radiation exposure limits (3.2)

Which ONE of the following is the LOWEST Emergency Classification that results in an automatic extension of annual dose (TEDE) limits for Emergency Response Organization (ERO) Personnel that have an NRC Form-4 on file and what is the dose limit extended to?

Q74 — EOP Continuous Action Verbs G2.4.17 Knowledge of EOP terms and definitions (3.9)

In accordance with OP-AA-101-111-1003, Use of Procedures, Salem EOPs' Continuous Action Steps are either surrounded by a shaded box or contain which of the following continuous action verbs?

1. ADJUST
2. CONTROL
3. MAINTAIN
4. MODIFY
5. MONITOR
6. VERIFY

Q75 — Containment Fire Response 2FP147 G2.4.25 Knowledge of fire protection procedures (3.3)

Given:

• Unit 2 is operating at 100 % Power.
• OHA A-7, FIRE PROT FIRE, annunciates.
• Panel 2RP5 is checked and indicates a Fire in Containment.
 ˆ Zone 59 — Air and Water Deluge, Containment El. 100 Panel 335 is lit.
 ˆ Zone 74 — Smoke and Fire Detector, Containment El. 100 Panel 335 is lit.
• The crew enters S2.OP-AB.FIRE-0001, Control Room Fire Response.
• The crew Trips the Reactor, Turbine, and all RCPs.
• 2-EOP-TRIP-1 is entered while continuing with S2.OP-AB.FIRE-0001, Control Room Fire Response.

Which ONE of the following describes the NEXT required action for the above conditions in accordance with S2.OP-AB.FIRE-0001?

Q76 — CCW Restoration After LBLOCA + LOOP 000011EA2.07 (3.4)

Given:
• Unit 2 is at 100% Power.
• 21 Auxiliary Feedwater Pump is cleared and tagged for motor replacement.
• 22 CFCU is cleared and tagged for bearing replacement.
• A Large Break LOCA occurs concurrently with a Loss of Off-Site Power.
• The crew is currently implementing step 17, "CCW Pump Operation Evaluation", in accordance with 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

Complete the following statement concerning component cooling water (CCW) system operation based on the above conditions:
The CRS will direct implementation of _(1)_ and the crew will start _(2)_.

Q77 — Loss of Charging Pump Tech Spec Entries 000022G2.2.22 (4.7)

Given:
• Unit 2 is at 100% Power.
• 21 Charging Pump is in service.
• 22 and 23 Charging Pumps are Operable.

Subsequently, the following sequence of events occurs:
• 21 Charging Pump trips due to a breaker malfunction.
• The CRS enters S2.OP-AB.CVC-0001, Loss of Charging, and starts 23 Charging Pump.

Based on the above conditions complete the following statements:

(1) The CRS will enter Technical Specification LCO(s) _(1)_.
(2) Assuming that 21 Charging Pump remains INOPERABLE for the next four (4) days, the CRS will place the Unit in _(2)_.

Note: 3.1.2.2, Reactivity Control Systems – Boration Flow Paths
   3.1.2.4, Reactivity Control Systems – Charging Pumps
   3.5.2, ECCS Subsystems

Q78 — CCW Abnormality RCP Bearing Temperature Time Limit 000026A2.06 (3.1)

Given:
• Unit 2 is at 100% Power.
• 22 Component Cooling Water Pump is cleared and tagged for maintenance.

At 1000:
• Bezel Alarm, SURGE TANK LEVEL HI-LO, is received.
• CCW Surge Tank Level is 35 % and lowering.
• Bezel Alarm, 21 (22) CC HDR PRESSURE LO, is received.
• OHA D-37, RCP BRG CLG HDR TEMP HI, is illuminated
• The crew has entered S2.OP-AB.CC-0001, Component Cooling Abnormality.
• The highest RCP Motor Bearing temperature is 140 °F and rising at 5 °F/minute

At 1005:
• Makeup to the CCW Surge Tank has been initiated and level is being maintained at approximately 40 %.
• OHAs D-20 through D-23; 21-24 RCP BRG CLG WTR FLO LO illuminate.

In accordance with S2.OP-AB.CC-0001, the EARLIEST time that the CRS will need to take action to prevent damage to the RCPs will be at ______.

Q79 — SGTR-1 Subcooling Loss Transition to SGTR-3 000038EA2.07 (4.8)

Given:
• The crew is performing 2-EOP-SGTR-1, Steam Generator Tube Rupture.
• Safety Injection has been terminated.
• The crew has just restored normal charging alignment per 2-EOP-SGTR-1, step 30 when RCS subcooling lowers to 0 °F.

In accordance with 2-EOP-SGTR-1, which ONE of the following completes the statement below:
The crew will start ECCS pumps as necessary to restore subcooling and ___________.

Q80 — LOPA-1 Decision Time for Extended Blackout [OUTDATED] 000055EA2.05 (3.7)

Given:
• Unit 2 is at 100% Power.
• A Loss of All AC Power occurs.
• The crew has entered 2-EOP-LOPA-1, Loss of All AC.
• Maintenance has reported that all three EDGs have been extensively damaged and restoration cannot be expected for at least 12 hours.
• The Load Dispatcher has informed the Shift Manager that restoration of Offsite Power cannot be expected for at least 24 hours.

In accordance with 2-EOP-LOPA-1, the CRS must make a decision within _(1)_ if AC power sources will be restored within the appropriate time requirements to support the SBO licensing basis, and then based on this decision the CRS will _(2)_.

Q81 — Grid Voltage Inoperable Lines 000077G2.1.7 (4.7)

Given:

• Unit 2 is at 100% Power.
• The voltages on the following 500 KV Lines are as follows:

Orchard (5021)	New Freedom (5024)	Salem-Hope Creek Tie (5037)
492 KV	495 KV	497 KV

Based on the above conditions, complete the following statements:

(1) The CRS will declare the __(1)__ 500 KV line(s) INOPERABLE.
(2) The CRS will direct performing __(2)__ of S2.OP-AB.GRID-0001, Abnormal Grid Disturbances.

Note: ESO = Electric System Operator

Q82 — Fuel Handling Incident Mast Tube 000036G2.1.32 (4.0)

Given:

• Unit 2 is in MODE 6.
• The Containment Equipment Hatch is closed.
• Core Reload is in progress.
• The transfer cart is in the Fuel Handling Building.
• A fuel assembly in the mast tube is in transit approaching the core.
• Gas bubbles are observed in the vicinity of the fuel assembly last placed in the core.
• The Refueling SRO has ordered all fuel transfers in progress stopped and all non-essential personnel evacuated from the containment.

Based on the above conditions, complete the statement concerning the NEXT action taken in accordance with S2.OP-AB.FUEL-0001, Fuel Handling Incident:

The CRS will direct placing the fuel assembly in the mast tube_________.

Q83 — Relay Room Fire PORV Block Valve 000067AA2.04 (4.3)

Given:

• Unit 2 is at 100% Power.
• The crew receives confirmation of a fire in the Unit 2 Relay Room.
• The crew enters S2.OP-AB.FIRE-0001, Control Room Fire Response.

In accordance with S2.OP-AB.FIRE-0001, Which ONE of the following completes the statements below?

At 2RP2 Panel, the crew will SELECT "FIRE ____(1)_____ CONTROL AREA".

Based on the location of the fire, the crew ____(2)_____ required to DISPATCH an Operator to align the PORV Block Valve circuits to EMERG CLOSE per S2.OP-AB.FIRE-0001 Attachment 15, "PORV – EMERG CLOSE/NORMAL ALIGNMENT".

Q84 — Natural Circ Cooldown Rates RVLIS 00WE10EA2.2 (3.9)

Given:

• Unit 2 tripped from 100% Power due to a Loss of Off-Site Power.
• It has been determined that a rapid natural circulation cooldown will be performed.

Complete the following statements concerning the procedural limitation in the natural circulation rapid cooldown rates of the RCS with and without RVLIS being available:

Note: 2-EOP-TRIP-5, Natural Circulation Rapid Cooldown with RVLIS
         2-EOP-TRIP-6, Natural Circulation Rapid Cooldown without RVLIS

The cooldown rate of the RCS with RVLIS available will be limited to less than __(1)__, and the cooldown rate of the RCS without RVLIS available will be limited to less than __(2)__.

Q85 — FRTS-1 Entry RCS Pressure Below 300 00WE08EA2.2 (4.1)

Given:

• Unit 2 is in MODE 3.
• RCS Temperature is 547°F
• RCS Pressure is 2235 psig.

Subsequently a LOCA occurs and the crew has transitioned from 2-EOP-TRIP-1, Reactor Trip or Safety Injection;

• RCS Pressure is 125 psig.
• RCS CETs read 380°F.
• RCS Cold Leg temperatures are 250°F.
• The RCS has cooled down > 100°F in the last 30 minutes.
• 22 RHR Pump failed to start.
• 21 RHR Pump is running providing 1150 gpm cold leg injection flow.

Based on the above conditions, complete the following statement;

Entry into 2-EOP-FRTS-1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITIONS is …

Q86 — CR Evacuation Seal Injection 003G2.4.34 (4.1)

Given:

• A Control Room Evacuation has been initiated on Unit 2 in accordance with S2.OP-AB.CR-0001, Control Room Evacuation.

In accordance with S2.OP-AB.CR-0001, which ONE of the following describes the procedural actions taken outside the control room to maintain seal injection flows to each Reactor Coolant Pump?

Note: 2CV71, Charging Header Pressure Control Valve
         2CV73, Seal Injection Pressure Control Bypass Valve
         2CV55, Charging Flow Control Valve

Q87 — LOCA Sump Blockage / ECCS Flow 006G2.4.47 (4.2)

Given:

• Unit 2 was initially at 100% Power.

At T+0:
• A Large Break LOCA occurs.
• Automatic Rx Trip, Safety Injection, and Containment Spray have actuated.
• The CRS has transitioned to 2-EOP-LOCA-3, Transfer to Cold Leg Recirculation, from 2-EOP-TRIP-1, Reactor Trip or Safety Injection, based on RWST levels reaching 15.2 feet.
• RO reports following status of 2-EOP-LOCA-3 actions:
    ◦ Containment Sump Levels are > 62 %
    ◦ 21 and 22 SJ44 (Containment Sump Valves) are open.
    ◦ 21 and 22 RHR Pumps are running.
    ◦ 2SJ69 (Common Suction) is stroking closed.

At T+16 minutes:
• The 2SJ69 valve is closed and the following indications are reported by the Reactor Operator:
    ◦ 21 and 22 RHR Pump amps are oscillating.
    ◦ 21 and 22 RHR Pump flows are oscillating.
    ◦ 21 and 22 RHR Pump discharge pressures are oscillating.

Note: 2-EOP-APPX-7, Containment Sump Blockage Guideline
         2-EOP-LOCA-5, Loss of Emergency Recirculation

Based on the above conditions, what procedure will the CRS enter NEXT to address this event and what is the MINIMUM ECCS Flow Rate required for decay heat removal at T+16 minutes?

[REFERENCES PROVIDED]

Q88 — Loss of VIB / ESFAS Phase B Logic 013A2.04 (4.2)

Given:
• Unit 2 is at 100% Power.
• A Loss of 2B Vital Instrument Bus has occurred.
• No operator action has been taken.

Complete the following statements concerning an impact on Engineered Safety Feature Actuation System (ESFAS) instrumentation due to the loss of the Vital Instrument Bus.

(1) Prior to any operator action taken, the current Containment Pressure channel logic (coincidence) for the remaining channels to cause a Phase B actuation is __(1)__.
(2) In accordance with Technical Specification 3.3.2.1, ESFAS Instrumentation, the CRS will direct maintenance to remove the inoperable channel from service by placing the Containment Pressure HI-HI Bistable in the __(2)__ condition.

Q89 — SW CFCU Isolation / Water Hammer 022A2.04 (3.2)

Given:

• Unit 2 is in MODE 4.
• Personnel performing work in Containment notify the Control Room of a large Service Water Cooler leak on 22 CFCU.
• The crew has entered S2.OP-AB.SW-0001, Loss of Service Water Header Pressure.

In accordance with S2.OP-AB.SW-0001, complete the following statements concerning isolating a service water leak on a CFCU:
(1) The CRS will direct stopping 22 CFCU and isolating the SW leak by closing the ____(1)___.
(2) The basis for this action is to ___(2)___.

Q90 — R18 Detector Failure / Liquid Release 073A2.02 (3.2)

Given:

• Unit 2 is at 100% Power.
• 21 CVCS Monitor Tank is in a recirculation lineup in accordance with S2.OP-SO.WL-0001, Release of Radioactive Liquid Waste from 21 CVCS Monitor Tank, in preparation for Chemistry Sampling and future release authorization by the Control Room Supervisor.

Complete the following statements concerning the expected response to the instrument failure and additional actions required in accordance with S2.OP-SO.WL-0001 to continue the liquid radioactive release based on the instrument failure.

(1) The 2R18 experiences a detector failure causing the monitor to fail LOW. The 2WL51, Liquid Release Stop Valve, __(1)__ automatically close.
(2) To continue the release, the CRS will verify 2FR1064, Radwaste Overboard Discharge Flow Recorder, is Operable __(2)__ perform two independent samples, independent release calculations, and independent discharge valve lineups.

Q91 — Loss of All Charging Pumps 011A2.04 (3.7)

Given:
• Unit 2 is in MODE 1 at approximately 8 % Power. Power ascension in progress.
• 23 Charging Pump is cleared and tagged for maintenance.
• 22 Charging Pump is in service.

Subsequently;

• 2C 4KV Bus de-energizes due to a differential fault on the bus.
• The crew starts 21 Charging Pump, but it trips on overcurrent.

Complete the following statement concerning the procedural action required to be taken. The CRS will initiate ___________.

Note: S2.OP-AB.4KV-0003, Loss of 2C 4KV Vital Bus
         S2.OP-AB.CVC-0001, Loss of Charging
         2-EOP-TRIP-1, Reactor Trip or Safety Injection

Q92 — Containment Hydrogen Concentration 028G2.1.20 (4.6)

Given:
• The Unit 2 crew is performing 2-EOP-LOCA-1, Loss of Reactor Coolant, Step 24, "Containment Hydrogen Concentration."
• Containment Hydrogen Concentration is 2.1 %.

In accordance with 2-EOP-LOCA-1, which of the following describes the required procedural action(s)?

Q93 — Condensate Pump Trip Actions 056A2.04 (2.8)

Given:
• Unit 2 is at 100% Power.
• All Condensate Pumps are in service.
• All Heater Drain Pumps are in service.
• The Condensate Polisher is in service.

Subsequently, 21 Condensate Pumps trips.

Complete the following statement regarding the required actions the CRS will direct in accordance with S2.OP-AB.CN-0001(Q), Main Feedwater / Condensate System Abnormality;

The CRS will direct the opening of the 21-23CN108, Polisher Bypass Valves if SGFP Suction Pressure is less than ___(1)___ and reduce Reactor Power to a MAXIMUM of ___(2)___.

Q94 — Refueling De-tensioning Requirements G2.1.40 (3.9)

Given:
Select from the choices below that contains ONLY actions directed to be performed in accordance with S2.OP-IO.ZZ-0007, Cold Shutdown to Refueling, BEFORE Reactor Head De-tensioning would be initiated for a refueling outage starting on November 1st.

1. The Reactor shall be subcritical for at least 168 hours.

2. Verify each valve that isolates unborated water sources is secured in the closed position.

3. Any two of the Source Range and/or Gamma-Metrics neutron monitors are Operable.

4. Continuous communications between the control room and refuel floor is established.

Q95 — Abnormal Secondary Chemistry G2.1.34 (3.5)

Given:
• Unit 2 is at 100% Power.
• Chemistry has removed the Condensate Polisher due to emergent issue and is NOT available for service.

Subsequently, the following alarms and indications are received in the Control Room:
• Bezel alarm CONDENSATE PUMP DISCH SODIUM HI.
• Bezel alarm HOTWELL OUTLET CONDUCTIVITY HI.
• Bezel alarm CONDENSATE PUMP DISCH CONDUCTIVITY HI.
• Condensate Pump Discharge sodium is 15 ppb.
• 21A Hotwell Cation Conductivity is 0.5 µS/cm and rising.
• Chemistry has validated a tube leak exists in the 21A Waterbox.

Assume the Chemistry parameters above continue over the next hour.
Which ONE of the following describes the actions required in accordance with S2.OP-AB.CHEM-0001, Abnormal Secondary Plant Chemistry?
[REFERENCE PROVIDED]

Q96 — Special Test or Evolution Screening G2.2.7 (3.6)

Given:

• Unit 2 is in MODE 5.
• A surveillance test is planned that involves a significant risk to Decay Heat Removal, if the test is not performed correctly a loss of Decay Heat Removal could occur.
• A Special Test or Evolution Coordinator has been assigned to determine if there is a need to implement special administrative and management controls in accordance with OP-AA-108-110, Evaluation of Special Tests or Evolutions.

Based on the above information, complete the following statements concerning special test or evolution conducted in accordance with OP-AA-108-110.

(1) The procedure or evolution is classified as a special test or evolution when the activity is complex __(1)__ infrequently performed.

(2) The __(2)__ approves IMPLEMENTATION of a special test or evolution.

Q97 — Protected Equipment Program G2.2.21 (4.1)

Given:

• Unit 1 is at 100% Power.
• 12 Charging Pump is scheduled to be cleared and tagged for Preventative Maintenance.
• The Preventative Maintenance Tasks are expected to take 24 hours to complete.

Complete the following statements concerning the implementation of OP-AA-108-116, Protected Equipment Program.

(1) The __(1)__ has overall authority of the protected equipment program.

(2) Prior to tagging 12 Charging Pump, redundant equipment must be protected when it's unavailability or manipulation could cause ___(2)___.

Q98 — Waste Gas Release Restrictions G2.3.11 (4.3)

Given:

• Unit 1 is shutdown during a refueling outage.
• A normal release of 14 Waste Gas Decay Tank to the plant vent is scheduled to be performed on day shift in accordance with S1.OP-SO.WG-0011, Discharge of 14 Gas Decay Tank (WGDT).

When reviewing the schedule, which of the following activities is procedurally allowed to be scheduled during the period 14 WGDT is being released?

Q99 — Emergency Coordinator Escalation G2.4.37 (4.1)

Given:
An event has occurred on Salem Unit 1:

• The TSC is ACTIVATED.
• The EOF is MANNED and NOT ACTIVATED.

In accordance with NC.EP-EP.ZZ-0102, Emergency Coordinator Response, which ONE of the following describes the individual responsible for escalating an emergency event level from a Site Area Emergency (SAE) to a General Emergency (GE)?

Q100 — EOP-TRIP-1 FRHS-1 Transition G2.4.14 (4.5)

Given:
Unit 2 was initially operating at 100% Power when the following sequence of events occurs;

• The reactor trips.
• A valid demand for Safety Injection occurs.
• The crew enters 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

Subsequently, the following occurs;

• 23 AFW Pump tripped on overspeed and cannot be reset due to trip throttle valve damage.
• 21 AFW Pump is tagged out for impeller replacement.
• 22 AFW Pump has tripped on motor overcurrent.
• All Steam Generator NR Levels are < 9%.
• All Steam Generator Pressures are stable.

Which ONE of the following indicates the proper procedural usage of the Emergency Operating Procedures (EOPs)?

Note: 2-EOP-FRHS-1, Loss of Secondary Heat Sink
         CFST, Critical Safety Function Status Trees