ML13191A869

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Initial 2013-301 Final RO Written Exam
ML13191A869
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 07/09/2013
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Download: ML13191A869 (82)
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NRC Exam Site-Specific RO Written Examination Applicant Information Name:

Date: June 28th, 2013 Facility/Unit: Browns Ferry Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time:

Instmctions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

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

Applicants Signature Results Examination Value 75 Points Applicants Score Points Applicants Grade Percent

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QUESTION 1 Unit 2 was operating at 100% power when the following occurs:

  • The 2B Reactor Recirc Pump trips
  • It is desired to operate in single loop for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Which ONE of the following completes the statements below?

The MCPR Reactor Core Safety Limit for SINGLE loop operation on Unit 2 is> (1)_.

The SINGLE loop limit(s) for(2) must be applied in accordance with Technical Specification 3.4.1, Reactor Coolant System (RCS).

A. (1)1.10 (2) Minimum Critical Power Ratio (MCPR) and Average Planar Linear Heat Generation Rate (APLHGR)

B. (1) 1.10 (2) Minimum Critical Power Ratio (MCPR) ONLY C. (1) 1.08 (2) Minimum Critical Power Ratio (MCPR) and Average Planar Linear Heat Generation Rate (APLHGR)

D. (1) 1.08 (2) Minimum Critical Power Ratio (MCPR) ONLY

QUESTION 2 Given Unit 2 is at 100% power with the following conditions:

  • Unit 2 I&C Cabinet 9-9-3 de-energizes Which ONE of the following completes the statements below?

[Assume no operator actions]

Reactor thermal power will _( 1).

Generator electrical output will (2).

A. (1) rise (2) rise B. (1) remain the same (2) lower C. (1) remain the same (2) remain the same D. (1) rise (2) lower

QUESTION 3 Given the following conditions:

  • A complete loss of 250 VDC Battery Board 2 occurs Which ONE of the following completes the statements below?

The NORMAL power supply to 250 VDC RMOV Bd _(l)_ has been lost.

After the RMOV Bd has been placed on its alternate power supply, operating a MOV that is powered from the board, for the purpose of completing a Tech Spec surveillance (2) allowed.

A. (l)2A (2) is B. (1)2A (2) is NOT C. (l)2C (2) is D. (l)2C (2) is NOT

QUESTION 4 Given the following conditions:

  • Reactor power is 29%
  • A Unit 1 startup is in progress
  • RPS A bus is lost due to a trip of the RPS MG A
  • Main Generator load is 295 MWe
  • Main Turbine 1st Stage Pressure on Panel 1-9-7 EHC WORK STATION is 145 psig
  • RPT LOGIC A TEST SWITCH (l-HS-099-5A-S14A) and RPT LOGIC B TEST SWITCH (l-HS-099-5A-S14B) are in NORMAL
  • Feedwater Level Control system is Three Element Control

A. BOTH Reactor Recirculation Pumps would trip B. ONLY the A Reactor Recirculation Pump would trip C. BOTH Reactor Recirculation Pumps would run back due to the 28% limiter D. The Reactor Recirculation Pumps would continue to operate at the current speed

QUESTION 5 Given the following conditions:

  • Unit 1 Reactor power is 100% when a reactor scram occurs
  • Twenty control rods are at position 02; all other rods are fully inserted
  • RPV level lowered to (-)40 inches and is recovering
  • Boron has NOT been injected Which ONE of the following completes the statements below?

According to l-EOI-l, RPV CONTROL, the reactor (1) remain shutdown under all conditions.

The procedure required to be used for Reactor Water Level Control is (2)_.

A. (1)willNOT (2) 1-C-5, LEVEL/POWER CONTROL B. (1)wiIINOT (2) the RC/L leg of l-EOI-1, RPV CONTROL C. (l)will (2) the RC/L leg of l-EOI-1, RPV CONTROL D. (l)will (2) 1-C-5, LEVEL/POWER CONTROL

QUESTION 6 Given the following conditions:

  • Unit 2 was operating at 100% power
  • The MSTVs automatically closed on high steam flow
  • The PCIS signal was not reset The operators arc carrying out the actions of 2-AOl-100-2, Control Room Abandonment, at Panel 2-25-32.

Which ONE of the following completes both statements below?

If the MAIN STEAM LINE A INBD ISOLATION VLV (MSIV) XFS switch, 2-XS-1-l4, is placed in EMERG while 2-HS-l-14C handswitch is positioned as shown above, this MSIV will

( 1 ).

After control is established at the Backup Control Panel, RCIC (2)_ trip on low suction pressure.

A. (1) remain CLOSED (2) will still B. (l)OPEN (2) will NOT C. (l)OPEN (2) will still D. (1) remain CLOSED (2) will NOT

QUESTION 7 Given the following conditions:

  • Unit 1 is operating at 100% Reactor Power
  • RBCCW PUMP DISCH HDR PRESS LOW, (l-9-4C, window 12), in alarm Which ONE of the following system loads is isolated from RBCCW cooling?

A. Drywell Blowers B. Drywell equipment drain sump heat exchanger C. Reactor Recirculation Pump seal coolers D. Reactor Building equipment drain sump heat exchanger

QUESTION 8 Given the following conditions:

  • All three Units are operating at 100% power
  • DIESEL GEN B TROUBLE (9-23B, Window 2) is in alarm The AUO who was dispatched to investigate, finds the following conditions on the B Emergency Diesel Generator:
  • The Left Bank Compressor breaker has tripped due to overload
  • The Left Bank Air Receiver pressure is 0 psig
  • The Right Bank Compressor is off
  • The Right Bank Air Receiver pressure is 160 psig and stable Which ONE of the following completes the statements below?

(1)_ of the diesel generator starting air systems is(are) required for Tech Spec 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air operability.

Given the conditions listed above, DG B _(2) required to be declared inoperable.

A. (1) ONLY one (2) is B. (1)ONLY one (2) is NOT C. (1) Both (2) is D. (1) Both (2) is NOT

QUESTION 9 Given the following initial conditions for Unit 3:

  • RPV level is 84 inches
  • 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE, is throttled to 8000 gpm
  • Reactor Recirc conditions are as indicated on the ICS RECIRC screen shot ICS RECIRC screen shot attached Which ONE of the following completes the statements below?

The current plant configuration (1) correct.

The indicated core flow is a result of(2).

A. (l)isNOT (2) forced flow from RHR System II ONLY B. (l)is (2) natural circulation C. (l)is (2) forced flow from RHR System II ONLY D. (l)isNOT (2) natural circulation

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QUESTION 10 A Subcriticality Check is in progress on Unit 2 in accordance with O-GOI-lOO-3C, Fuel Movement Operations During Refueling, Attachment 7.

  • 8 Shorting Links are attached to the Unit 2 Rx Mode Switch
  • A control rod surrounded by fuel is being withdrawn Which ONE of the following completes the statements below?

The SRMS are placed in the non-coincident mode because (1).

With ALL shorting links removed, (2)_ are in the non-coincident mode.

A. (1) a spiral reload is in progress (2) the SRMs ONLY B. (1) the SRMs are quadrant specific (2) the SRMs ONLY C. (1) a spiral reload is in progress (2) ALL neutron monitors D. (1) the SRMs are quadrant specific (2) ALL neutron monitors

QUESTION 11 Given the following conditions:

  • Unit 1 was operating at 50% power
  • Drywell temperature and pressure began to slowly rise
  • Operators entered 1 -AO1 1, Drywell Pressure and/or Temperature High, or Excessive Leakage Into Drywell
  • Drywell pressure reached 2.0 psig, the operators inserted a manual scram After completing the immediate operator actions for 1-AOI-l00-1, Reactor Scram, the following conditions exist:
  • Reactor water level is (-)l0 inches with level slowly rising
  • Reactor pressure is steady at 960 psig
  • Drywell pressure is 2.3 psig and slowly rising
  • Drywell temperature is 150° F and slowly rising Which ONE of the following completes the statement below?

Based on these conditions, the operating crew is required to A. continue in l-AOI-64-l and 1-AOI-lOO-l, ONLY B. enter EOI-1, RPV Control, ONLY, and exit l-AOI-64-l and l-AOI-l00-1 C. enter EOI-l, RPV Control, and continue in 1-AOI-64-1 and l-AOI-100-l D. enter EO1- 1, RPV Control and EOI-2, Primary Containment Control, and exit 1-AOl- 100-1, and 1-AOI-64-1

QUESTION 12 Given the following conditions:

  • Unit 3 Reactor operating at 100% power
  • A failure in the EHC System causes reactor pressure to slowly rise Which ONE of the following places the below list of events in the proper sequence?
1. Reactor scram on high pressure
2. REACTOR PRESS HIGH aimunciator (9-5A, Window 1) alarms
3. First Group of Main Safety Relief Valves (MSRV5) opens
4. Technical Specification LCO 3.4.10 Reactor Steam Dome Pressure, LCO exceeded
5. ATWS AUTO INITIATE (9-4A, Window 10)

A. 2,4, 1,3 B. 2,4,1,5 C. 4,2,1,3 D. 4,2,5,3

QUESTION 13 Given the following conditions:

  • Unit 2 was at 100% power
  • BOTH loops of RHR are in Suppression Pool Cooling mode
  • Drywell Pressure is 1.8 psig and steady
  • Suppression Chamber Pressure 3.3 psig and steady
  • Suppression Pool Level 11.4 feet and steady
  • Suppression Pool Temp 140°F and lowering
  • RHR A and C loop flow @ 11500 gpm
  • RHR B and D loop flow 13200 gpm
  • RHRSW D flow @ 4400 gpm IREFERENCE PROVIDEDI Based on these conditions, which ONE of the following describes the required operator action and the reason?

A. Match Loop I RHRSW pump flows to meet operating limits B. Reduce Loop II RHRSW pump flows to ensure flow rate capability remains on the non LOCA units C. Reduce Loop II RHR system flow because it has exceeded operating limits D. Raise Suppression Pool level to prevent RHR Pumps from air entrainment due to vortex limit concerns

QUESTION 14 Unit 2 was operating at 100% power when a small steam leak caused an automatic scram.

Given the following conditions:

  • RPV Pressure is 900 psig and steady
  • RPV Level is (+)25 inches and steady
  • Drywell Pressure is 10 psig and slowly rising
  • Suppression Chamber Pressure is 8.5 psig and slowly rising
  • Drywell Temperature is 165° F and slowly rising
  • Suppression Pool Level is (-) 11 inches
  • Suppression Pool Temperature is 90° F Which ONE of the following describes the NEXT action required by 2-EOI-2, PRIMARY CONTAINMENT CONTROL and the reason for that action?

A. Operate drywell sprays because the drywell pressure is high B. Operate all available drywell coolers because the drywell temperature is high C. Emergency depressurize because the suppression chamber pressure is high D. Emergency depressurize because the suppression pooi level is low

QUESTION 15 Which ONE of the following completes the statement below?

In accordance with 1 -EOI-2, Primary Containment Control, Step SP/L- 17, If suppression pool level cannot be maintained above a minimum level of (1), HPCI is required to be secured because _(2)_.

A. (1) 12.75 ft (2) the turbine steam exhaust line is uncovered B. (1) 12.75 ft (2) of insufficient lube oil cooling C. (1) 11.5 ft (2) the turbine steam exhaust line is uncovered D. (1) 11.5 ft (2) of insufficient lube oil cooling

QUESTION 16 Given the following conditions:

  • A Loss of Coolant Accident has occurred on Unit 1
  • RPV level can NOT be maintained and Primary Containment flooding is required per step C 1-26 Which ONE of the following completes the statement below?

The core is adequately cooled if the MIMINUM RPV Water level is at or above (1) inches and the Core Spray System is operating with a MINIMUM of(2)_.

A (1) (-)215 (2) two loops injecting at 3125 gpm each B. (1) (-) 180 (2) two loops injecting at 3125 gpm each C. (1) (-)215 (2) one ioop injecting at 6250 gpm D. (1) (-) 180 (2) one loop injecting at 6250 gpm

QUESTION 17 Given the following conditions:

  • Initial power level after the scram was 23%

Currently:

  • SLC Storage Tank Level is 63%
  • RPV Pressure is 900 psig and steady
  • RPV Level is (-)90 inches
  • LRMS are inserted and indicating on Ranges 4 and 5
  • SRMs are inserted and indicating between 1O and 106 CPM
  • SRM period indication is -40 seconds Which ONE of the following completes the statements below?

At this time, the reactor _(l) subcritical.

If, at this SLC tank level, RPV Water level is restored to (+)2 to (+)5 1 inches, the reactor will be (2).

A. (l)isNOT (2) critical B. (l)is (2) critical C. (1) is (2) subcritical D. (1) is NOT (2) subcritical

QUESTION 18 Given the following conditions:

  • Unit 2 is performing a startup
  • STACK GAS RADIATION HIGH (2-9-3A, Window 13) is in alarm
  • OG POST-TREATMENT RADIATION HIGH, (2-9-4C, Window 33) is in alarm
  • OG POST TREATMENT RADIATION HIGH-HIGH (2-9-4C, Window 34) is in alarm
  • OG POST-TREATMENT CH A RAD MON RTMR, 2-RM-90-265A, is reading 6.5x 10 cps
  • OG POST-TREATMENT CH B RAD MON RTMR, 2-RM-90-265B, is reading 6.3x 10 cps
  • The Off Gas Treatment Select Switch, 2-XS-66-1 13, is in BYPASS Which ONE of the following identifies the AUTOMATIC actions (if any) of the Offgas system to limit the offsite release rate?

A. Adsorber Bypass Valve, 2-FCV-66-113B will CLOSE.

Adsorber Inlet Valve, 2-FCV 1 13A will OPEN Charcoal Adsorber Train 2 Inlet Valve, 2-FCV 118 will OPEN B. Adsorber Bypass Valve, 2-FCV-66-1 13B will CLOSE NO other valves will reposition C. Adsorber Bypass Valve, 2-FCV-66-113B will CLOSE Adsorber Inlet Valve, 2-FCV 1 13A will OPEN NO other valves will reposition D. NO valves will reposition

QUESTION 19 Given the following conditions on Unit 1:

  • The Fire Protection System is in a normal lineup with the Fire Pump Selector Switch (XS-26-43 on panel 9-20) in position CAB
  • A loss of offsite power has occurred
  • Reactor water level is (-)130 inches and stable Subsequently:
  • An AUTOMATIC sprinkler actuation signal is received from a Unit 1 Reactor Building sensor
  • With NO operator action, Fire Header pressure is 125 psig, fifty (50) seconds after the actuation signal is received Which ONE of the following describes the status of the Electric Driven Fire Water Pumps?

A. ALL Electric Driven Fire Pumps are operating B. ALL Electric Driven Fire Pumps are locked out for AUTOMATIC start C. ONLY the C Electric Driven Fire Pump is operating D. ONLY the B Electric Driven Fire Pump is operating

QUESTION 20 Given the following conditions:

  • All units are operating at 100% RTP with lagging VARS
  • Current system voltage is 542KV
  • Current system frequency is 60.03 hz Which ONE of the following completes the statements below?

The operators will coordinate between the units and, as directed by 0-AOI-57-1E, Grid Instability, lower_( 1 )_.

This will cause the power factor to (2)_.

A. (1) reactor power approximately 1% per minute using the recirc master control buttons (LOWER SLOW 1, 2, 3-HS-96-33 or LOWER MEDIUM 1, 2, 3-HS-96-34)

(2) rise (closer to 1.0)

B. (1) reactor power approximately 1% per minute using the recirc master control buttons (LOWER SLOW 1, 2, 3-HS-96-33 or LOWER MEDIUM 1, 2, 3-HS-96-34)

(2) drop (further from 1.0)

C. (1) reactive power using VOLTAGE REGULATOR RAISE LOWER ADJUST (1,2,3 HS-57-26)

(2) rise (closer to 1.0)

D. (I) reactive power using VOLTAGE REGULATOR RAISE LOWER ADJUST (1, 2, 3 HS-57-26)

(2) drop (further from 1.0)

QUESTION 21 In accordance with 1-AOI-3-1, Loss of Reactor Feedwater or Reactor Water Level High/Low, which ONE of the following identifies a consequence of allowing water level to rise to the point that water enters the main steam lines?

A. The safety relief valves could fail to OPEN B. The safety relief valves could fail to CLOSE C. RCIC damage could occur D. HPCI damage could occur

QUESTION 22 Given the following conditions:

  • Unit 3 is operating at 65%
  • Reactor Power is rising steadily
  • RPV Water Level is 33 inches and stable
  • Generator Output is rising steadily Which ONE of the following identifies the cause of the above indications?

A. One MSRV is failing open.

B. The A Low Pressure Feedwater Heater String (Heaters 3A3, 3A4, 3A5) is isolating.

C. The B Main Steam Line Flow Instrument (3-FI-46-2) is slowly failing low.

D. One of the Recirc speed controllers is slowly failing high.

QUESTION 23 Given the following conditions:

  • A hydraulic ATWS has occurred on Unit 3
  • Reactor power is 28%
  • MSlVareopen
  • Reactor pressure is being maintained on the bypass valves
  • All control rods inserted at least one notch on the scram Which ONE of the following completes the statements below?

At this time the Rod Worth Minimizer _(l)_ enforcing an INSERT BLOCK.

The RWM LOW POWER SETPOINT (LPSP) is based on _(2)_.

A. (l)is (2) ONLY reactor steam flow B. (1)is (2) reactor steam flow and feed flow C. (l)isNOT (2) reactor steam flow and feed flow D. (l)isNOT (2) ONLY reactor steam flow

QUESTION 24 Given the following conditions:

  • A complete steam line rupture in the Turbine Building occurred
  • RCIC STEAM LINE LEAK DETECTION TEMP HIGH is in alarm
  • RCIC room temperature on l-TE-071-0041 reached 160° F
  • All other RCIC area temperatures reading between 130° F to 135° F (Peak values)
  • Drywell temperature 143° F
  • Drywell pressure 2.6 psig
  • Suppression pooi level (-) 1.5 inches
  • Suppression pooi temperature is 107° F
  • RPV Level is (+)30 inches with HPCI injecting to the vessel
  • RPV Pressure is being controlled 800 to 1000 psig with the SRVs
  • PCIS Groups 2,3,5, 6, and 8 are isolated Which ONE of the following completes the statements below?

The Group 5 isolation (1)_.

EOI-3 entry (2) required.

A. (1) occurred as designed (2) is B. (1) occurred as designed (2) is NOT C. (1) should NOT have occurred (2) is D. (1) should NOT have occurred (2) is NOT

QUESTION 25 Given the following conditions:

  • A small break LOCA concurrent with a LOOP has occurred on Unit 1
  • HPCI was manually initiated in accordance with Appendix 5D and is required to maintain RPV water level
  • Drywell pressure is 15 psig
  • RCIC is unavailable Subsequently:
  • HPCI LEAK DETECTION TEMP HIGH (9-3F, Window 10) is received due to a steam break in the HPCI room Which ONE of the following completes both statements below?

In accordance with ARP 9-3F, window 10, the _(l) may give erroneous indications due to high temperatures in secondary containment.

In accordance with EOI-3, HPCI (2) required to be isolated.

A. (1) SUPP CHBR WTR LVL, 1-LT-64-159 (2)is B. (1) SUPP CHBR WTR LVL, 1-LT-64-159 (2) is NOT C. (1) SHUTDOWN FLOODUP, 1-LI-3-55 (2) is NOT D. (1) SHUTDOWN FLOODUP, 1-LI-3-55 (2) is

QUESTION 26 Given the following conditions:

  • Unit 2 scrammed
  • RX BLDG AREA RADIATION HIGH (Panel 9-3A Window 22) is in alarm
  • RB EL 565E CRD-HCU EAST 2-RE-90-21A is reading 450 mRibr and slowly rising
  • All other area radiation monitors are reading normally
  • No Reactor Building area temperatures are in alarm Which ONE of the following completes both of the statements below?

Based on the location of this alarm, EOI-3 Table 4, Secondary Containment Area Radiation, indicates that a potential isolation source is the _(l).

The MINIMUM required action(s) to isolate the leak is/are to_(2).

A. (1) Reactor Water Cleanup System (2) close RWCU INBD SUCTION ISOLATION, 2-FCV-69-l, RWCU OUTBD SUCTION ISOLATION, 2-FCV-69-2, and RWCU RETURN ISOLATION VALVE, 2-FCV-69-l2 B. (1) Reactor Water Cleanup System (2) close RWCU INBD SUCTION ISOLATION, 2-FCV-69-l and RWCU OUTBD SUCTION ISOLATION, 2-FCV-69-2 ONLY C. (1) Scram Discharge Volume vents and drains (2) depress the NORMAL/ISOLATE pushbutton at the SDV Display on Panel 2-9-5 ONLY D. (I) Scram Discharge Volume vents and drains (2) place the SCRAM DISCH VOLUME HI LEVEL BYPASS, 2-HS-99-5A-S4, keylock switch in BYPASS, and then depress the NORMAL/ISOLATE pushbutton at the SDV Display on Panel 2-9-5

QUESTION 27 Given the following conditions:

  • Unit 2 RHR Loop I is in suppression pooi cooling
  • A 75 gpm RHRSW leak occurs in the RHR heat exchanger room Which ONE of the following completes the statements below?

The FIRST available indication to the operators that entry into 2-EOI-3 is required is (1).

If, while executing 2-EOl-3, water level continues to rise, the operators (2) determine when area water level reaches 20 inches using Control Room alarms.

A. (1) a high level alarm on control room panel 9-4C (2) can B. (1) a high level alarm on control room panel 9-4C (2) can NOT C. (1) high level alarm in the radwaste control room (2) can D. (1) high level alarm in the radwaste control room (2) can NOT

QUESTION 28 Given the following conditions:

  • A LOCA has occurred on Unit 3
  • The lowest RPV level reached during the transient was (-) 190 inches
  • RPV Level is 33 inches and slowly rising
  • RPV Pressure is 200 psig
  • Drywell Pressure is 8 psig
  • RHR Loop I is currently injecting with two (2) pumps at 17,000 gpm
  • RHR Loop II is in suppression pooi cooling
  • LPCI AUTO-TNT LOGIC A (B) SEALED IN (3-IL-74-151 and 152) are illuminated NOTE:
  • 3-XS-74-122 is the RHR SYS I LPCI 2/3 CORE HEIGHT OVRD switch
  • 3-HS-74-155A is the LPCI SYS I OUTBD INJ VLV BYPASS SEL switch Which ONE of the following is (are) the MINIMUM operator action(s) necessary to reduce RHR flow and stabilize level per 3-EOI APPENDIX 6B, INJECTION SUBSYSTEMS LINEUP RHR SYSTEM I LPCI MODE?

A. Throttle 3-FCV-74-52 ONLY B. Place 3-HS-74-155A in BYPASS, and throttle 3-FCV-74-52 ONLY C. Place 3-XS-74-122 in MANUAL OVERRIDE, and throttle 3-FCV-74-52 ONLY D. Place 3-HS-74-155A in BYPASS, place 3-XS-74-122 in MANUAL OVERRIDE, and throttle 3-FCV-74-52

QUESTION 29 Given the following conditions:

  • Unit 2 has been scrammed
  • 2-DRV-010-0505, RPV DRAIN TO RWCU, is OPEN
  • 2-SR-3.4.9.1(1), Reactor Heatup and Cooldown Rate Monitoring, Attachment 1, Reactor Heatup and Cooldown Rate Monitoring is being performed The following data has been recorded:

At 1600:

Steam Dome Pressure 50 psig Rx Vessel Drain Temp ICS Point ID 56-8 28 1°F Rx Vessel Head Temp ICS Point ID 56-1 3 10°F At 1630:

Steam Dome Pressure 20 psig Rx Vessel Drain Temp ICS Point ID 56-8 250°F Rx Vessel Head Temp ICS Point ID 56-1 260°F Which ONE of the following is the calculated cooldown RATE in accordance with 2-SR-3.4.9. 1(1)?

IREFERENCE PRO VIDEDI A. 31°F/HR B. 39°F/HR C. 62°F/HR D. 78°F/HR

QUESTION 30 Which ONE of the following completes the statements below?

[consider each statement separately]

With Unit 2 in MODE 3 at 160 psig, HPCI (1) required by Technical Specifications to be OPERABLE.

In accordance with BFN 0DM 4.20, Strategies for Successful Transient Mitigation, if HPCI initiates on a high drywell pressure signal, and HPCI IS NOT needed for reactor water level control, then (2)

A. (1) is (2) trip HPCI and place the Aux Oil Pump (AOP) control switch in Pull- to-Lock (PTL)

B. (1)isNOT (2) trip HPCI and place the Aux Oil Pump (AOP) control switch in Pull- to-Lock (PTL)

C. (l)is (2) trip HPCI and ensure the Aux Oil Pump (AOP) control switch remains in the AUTO position D. (l)isNOT (2) trip HPCI and ensure the Aux Oil Pump (AOP) control switch remains in the AUTO position

QUESTION 31 Given the following conditions:

  • Unit 1 was operating at 80%
  • Core Spray pump 1A is running for l-SR-3.5.l.6, Core Spray Flow Rate Loop I, with system flow of 3200 gpm and discharge pressure of 240 psig
  • Drywell pressure 11 psig
  • Reactor water level (-)65 inches
  • Reactor pressure 400 psig Which ONE of the following completes the statements below?

Core Spray Pump lA Discharge Pressure will _(l)_.

Core Spray Loop I _(2) injecting to the reactor.

A. (1) REMAIN THE SAME (2) is B. (1) RISE (2) is NOT C. (1) RISE (2)is D. (1) REMAIN THE SAME (2) is NOT

QUESTION 32 Which ONE of the following completes the statements below?

The Standby Liquid Control System shares an RPV penetration with an instrument tap for the (1) annunciator.

The Standby Liquid Control System injection line terminates at and disperses sodium pentaborate slightly (2)_ the reactor core plate.

A. (1) CORE SPRAY SYS I SPARGER BREAK, Panel 9-3C, window 14 (2) above B. (1) CORE SPRAY SYS I SPARGER BREAK, Panel 9-3C, window 14 (2) below C. (1) RX PRESS LOW CORE SPRAY/RHR PERMISSIVE, Panel 9-3C, window 35 (2) above D. (1) RX PRESS LOW CORE SPRAY/RHR PERMISSIVE, Panel 9-3C, window 35 (2) below

QUESTION 33 Given the following conditions:

  • A Unit 1 ATWS occurred
  • During the performance of 1-EOI-Appendix 3A, SLC INJECTION, the Standby Liquid Control (SLC) pump control switch was placed in the START-A position
  • RPV pressure is 1020 psig
  • SLC discharge pressure is 1100 psig
  • SQUIB VALVE A CONTINUITY blue light is illuminated
  • SQUIB VALVE B CONTINUITY blue light is extinguished
  • SLC SQUIB VALVE CONTINUITY LOST(Panel 1-9-5B, Window 20) is in alarm
  • SLC INJECTION FLOW TO REACTOR (Panel 1-9-5B, Window 14) is in alarm Which ONE of the following completes the statements below?

The SLC Squib valve _( 1 )_ is OPEN.

The time to inject Hot Shutdown Boron Weight is (2) compared to the time with both squib valves open.

A. (l)B (2) the same B. (l)A (2) longer C. (1)B (2) longer D. (l)A (2) the same

QUESTION 34 Given the following conditions:

  • Unit 3 is operating at 90% and Turbine Stop Valve Closure-RPS Trip Logic System Function Test, 3-SR-3.3.l.1.14 (81), is being performed
  • On panel 3-9-7, the Unit Operator depresses and holds MSV-l TEST pushbutton 3-HS-47-141 until the MSV- 1 position indicator 3-ZI- 1-74 indicates 0%

Which ONE of the following completes the statements below?

The RPS Trip Logic senses Main Turbine Stop Valve, MSV- 1, CLOSED when the valve position first reaches a setpoint of(1)_.

During this surveillance step, annunciator RPT SYS A TRIP (3-9-4A, window 11) (2) alarm.

A. (1) <90% OPEN (2) will NOT B. (1)<5%OPEN (2) will NOT C. (l)<90% OPEN (2) will D. (1) <5% OPEN (2) will

QUESTION 35 Given the following conditions:

  • A Unit I plant startup is in progress
  • The REACTOR MODE SELECTOR switch is in STARTUP
  • IRM C indicates 57/125 on Range 6
  • IRM H indicates 27/125 on Range 6 Which ONE of the following describes the conditions that will occur if IRM C and IRM H are ranged down to Range 5?

A. Rod Block from IRM C ONLY B. Rod block from both IRM C and H ONLY C. Rod block AND a Half scram ONLY D. Rod block AND a Full scram

QUESTION 36 Given the following conditions:

  • Unit 1 plant startup is in progress
  • SRM A drawer in Panel 3-9-12, loses power
  • All IRMs are on range 4
  • The RPS shorting links are installed Which ONE of the following completes the statement below?

The power supply to the SRM A drawer is _(1).

The plant response to the SRM A loss of power is _(2).

A. (1) 120 VAC (2) a half scram and rod block B. (1)+/-24VDC (2) a half scram and rod block C. (1)+/-24VDC (2) a rod block ONLY D. (1) 120 VAC (2) a rod block ONLY

QUESTION 37 Which ONE of the following completes the statements below for the Unit 2 APRM power supply arrangement?

Each APRM is (1) at Panel 2-9-14.

Within a Quad Low Voltage Power Supply (QVPS), Low Voltage Power Supplies (LVPS) 1 and 2 are powered from (2)_.

A. (1) only powered from the QLVPS located in its associated bay (2) RPS B B. (1) only powered from the QLVPS located in its associated bay (2) RPS A C. (1) powered from two QLVPS (2) RPS B D. (1) powered from two QLVPS (2) RPS A

QUESTION 38 With Unit 2 in Mode 1 the following surveillance is in progress:

  • 2-SR-3.5.3.3, RCTC System Rated Flow at Normal Operating Pressure
  • RCIC SYSTEM FLOW/CONTROL, 2-FIC-71-36A is in AUTO and set at 620 GPM While establishing RCIC Pump discharge pressure 80 psig greater than reactor pressure, the Operator inadvertently fully CLOSES the RCIC PUMP CST TEST VLV, 2-FCV-71-38.

Which ONE of the following completes the statements below?

The RCIC PUMP MIN FLOW VALVE, 2-FCV-7l-34A 1)_ automatically open.

RCIC Turbine Speed will _(2)_.

A. (1) will (2) decrease B. (l)will (2) increase C. (l)willNOT (2) decrease D. (1) will NOT (2) increase

QUESTION 39 Given the following conditions:

  • The UO closed and then re-opened the RCIC TURBINE TRIP/THROTTLE VALVE, 2-FCV-7 1-9 The following RCIC indications exist:
  • RCIC TURB TRIP/THROTTLE VALVE, 2-ZI-71-9 green light ON, red light OFF
  • Hands witch RCIC TURB TRIP/THROTTLE VALVE, 2-HS-7 1-9 red light ON, Green light OFF
  • RCIC TURBINE CONTROL VALVE, 2-FCV-7 1-10 green light ON, red light ON Which ONE of the following completes the statement below?

RCICis A. tripped on overspeed B. reset and will start as soon as RCIC TURBINE STEAM SUPPLY VLV, 2-FCV-71-8, first begins to open C. reset and will start after RCIC TURBINE STEAM SUPPLY VLV, 2-FCV-71-S, has reached its full open position D. tripped on high water level

QUESTION 40 Given the following conditions:

  • Unit I was operating at 100% Reactor Power
  • RHR Pump 1D is tagged Subsequently:
  • A Loss of Coolant Accident and a Loss of Off Site Power occur
  • Reactor Water Level is (-)125 inches
  • Drywell Pressure is 4.1 psig
  • A and C 4KV Shutdown Boards are de-energized

A. Place ONLY ADS Logic Inhibit Switch A to INHIBIT B. Place ONLY ADS Logic Inhibit Switch B to INHIBIT C. Place BOTH ADS Logic Inhibit Switches A AND B to INHIBIT D. NO action is required

QUESTION 41 Given the following plant conditions:

  • During performance of 2-SR-3.3.l. 1.13, Reactor Protection and Primary Containment Isolation Systems Low Reactor Water Level Instrument Channel B2 Calibration, 2-LIS-3-203D, RX WATER LEVEL LOW, fails to actuate.
  • The Shift Manager has determined that the proper action is to trip the inoperable channel by removing fuse 2-FU1-3-203DA ONLY.

Which ONE of the following completes the statement below in accordance with 2-01-64, Primary Containment System and 2-01-99, Reactor Protection System (RPS)?

When the fuse is removed, the operator in the control room will observe (1), and (2).

A. (1) all four lights over the PCIS Reset Switches on Panel 9-4 remain illuminated (2) a half scram B. (1) one of the lights over the PCIS Reset Switches on Panel 9-4 will extinguish (2) NO half scram C. (1) one of the lights over the PCIS Reset Switches on Panel 9-4 will extinguish (2) a half scram D. (1) all four lights over the PCIS Reset Switches on Panel 9-4 remain illuminated (2) NO half scram

QUESTION 42 Given the following condition:

  • Reactor pressure is slowly lowering Which ONE of the following completes the statement below in accordance with 1-01-1, Main Steam, Section 3.2.2.B?

When reactor pressure FIRST reaches _( 1 )_ and the reactor mode switch is in the _(2)_

position, the MSIVs will auto-close.

A. (l)852psig (2) START/HOT STBY B. (l)852psig (2) RUN C. (l)725psig (2) START/HOT STBY D. (1) 725 psig (2) RUN

QUESTION 43 Which ONE of the following completes the statement below?

On Unit 2, (l)_ are equipped with accumulators, which are sized to contain sufficient pneumatic pressure for a minimum of 5 _(2).

A. (1) ALL MSRVs (2) valve operations B. (1) ONLY the ADS MSRVs (2) valve operations C. (1)ALLMSRVs (2) hours D. (1) ONLY the ADS MSRVs (2) hours

QUESTION 44 Given the following condition:

  • Unit 3 is at 85% power
  • Reactor Vessel Narrow Range instrument, LT-3-53, has a small leak on the reference leg tap
  • The Feedwater Level Control System (FWLCS) is in 3-element control The Narrow Range instruments indicate as follows:
  • LT-3-53 44 inches
  • LT-3-60 33 inches
  • LT-3-206 31 inches
  • LT-3-253 33 inches Which ONE of the following indicates the Reactor Vessel Level that the FWLCS is using as the current RPV level?

A. 37 Inches B. 35 inches C. 33 inches D. 32 inches

QUESTION 45 Which ONE of the following completes the statement below?

When the SBGT charcoal filter temperature first reaches_(l )_ due to iodine adsorption following a LOCA, the decay heat removal dampers _(2) once the train has been shutdown.

A. (1) 125° F (2) automatically open B. (1) 150°F (2) automatically open C.(1) 125°F (2) must be manually opened D. (1) 150° F (2) must be manually opened

QUESTION 46 Which ONE of the following completes the statements below?

There are _(1) 500KV Off-site Lines connected to the Browns Ferry Switchyard.

The capacitor banks at Browns Ferry are physically connected directly onto 16 1KV bus

_(2).

A. (1) five (2) 2 (Athens)

B. (1) seven (2) 2 (Athens)

C. (1) five (2) 1 (Trinity)

D. (1) seven (2) 1 (Trinity)

QUESTION 47 Given the following conditions on panel 0-9-23-7:

  • 0-43-2 1 1-A, 4kV SD BD A AUTO/LOCKOUT RESET switch is in the TRIPPED condition
  • 4kV SD BD A NORM FDR BKR 1614 is OPEN Which ONE of the following completes the statement below if the Unit Operator places the 0-43-211-A switch to the RESET position?

The Shutdown Board will _(1) Transfer AND will be supplied from (2).

A. (1) FAST (2) Shutdown Bus 1 B. (1) SLOW (2) Shutdown Bus 1 C. (1) FAST (2) Shutdown Bus 2 D. (1) SLOW (2) Shutdown Bus 2

QUESTION 48 Given the following conditions:

  • Unit 2 is operating at 90%
  • An electrical fault occurs causing a loss of Unit Preferred Panel 2-9-9 Cabinet 6 Which ONE of the following completes the statements below?

In accordance with 2-AOI-57-4, Loss of Unit Preferred, the power to is (are) lost.

A. RFWCS Panel Display Stations B. SRV Acoustic Monitors on Panel 9-3 C. CRD System Flow Control Valves, 2-FCV-85-1 1 A / B D. CRD Accumulator Pressure and Level Instruments

QUESTION 49 The following are indicated on Battery Board 2 Panel 1:

  • BATTERY BOARD 2 250V DC BUS GND INDICATOR 0-GI-280-0002/103 is (-)4V
  • BATTERY BOARD 2 250V DC BUS VOLTMETER(0-E1-280-0002/102) indicates 255 VDC
  • BATTERY 2 AMMETER (0-11-280-0002/101) indicates as shown:

The following are indicated on 250V Battery Charger 2A:

  • Charger DC Voltage is 255 VDC
  • AC ON light is lit
  • All other lights are extinguished
  • The equalize timer is set for 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Which ONE of the following predicts the expected Battery Board 2 Panel 1 voltage trend and the reason for that trend with NO operator action?

A. LOWER, because the bus load exceeds the chargers capacity B. LOWER, because a ground exceeding the allowable normal value is indicated C. REMAIN THE SAME, because the chargers output voltage is the same as the battery board voltage D. REMAIN THE SAME, because the charger is on float charge

QUESTION 50 All three units were initially operating at 100% power when the following occurred:

  • Offsite power was lost to the entire site
  • EDG 3EA failed to start and cannot be manually started
  • A Unit 2 accident signal is received Which ONE of the following completes the statement below?

25OVDC Battery Chargers have received a 480V load shed signal.

A. 1,2A,2B,and4 B. 2A and 2B ONLY C. 1,2A,and2BONLY D. l,2A,2B,and3

QUESTION 51 All three units were initially operating at 100% power when the following occurred:

  • A loss of offsite power to the entire site
  • An accident signal is received on Unit 3 Subsequently:
  • 1 minute later Diesel Generator 3EB trips on overspeed Which ONE of the following describes the current status of the 3A and 3B Core Spray pumps?

3A Core Spray pump 3B Core Spray pump A. NOT Running Running B. Running NOT Running C. NOT Running NOT Running D. Running Running

QUESTION 52 Given the following conditions:

  • All three Units are operating at 100% power
  • Control Air Compressors in their normal line up
  • AIR COMPRESSOR ABNORMAL, 1-9-20 (Window 29) is in alarm
  • CONTROL AIR PRESSURE, on Panel 1-9-20, indicates 84 psig and lowering Which ONE of the following completes the statements below?

The cause of the AIR COMPRESSOR ABNORMAL annunciator is (1).

The operator required action(s) per 0-AOI I, Loss of Control and Service Air Compressors, is (are) to (2).

A. (1) a trip of Air Compressor F (2) verify OPEN 2-FCV-32-28, 29, and 91, CONTROL AIR ISOLATION VALVE SECONDARY CTMT B. (1) a trip of Air Compressor F (2) verify OPEN 0-PC V-33-1, SERVICE AIR TO CONTROL AIR ISOLATION VALVE C. (1) a trip of Air Compressor G (2) verify OPEN 2-FCV-32-28. 29, and 91, CONTROL AIR ISOLATION VALVE SECONDARY CTMT D. (1) a trip of Air Compressor G (2) verify OPEN 0-PCV-33-1, SERVICE AIR TO CONTROL AIR ISOLATION VALVE

QUESTION 53 Given the following conditions:

  • All three units are operating at 100% power
  • The operating A3 EECW Pump trips
  • The C3 EECW pump fails to start Which ONE of the following describes the impact of the A3 EECW Pump trip and failure of the C3 EECW pump to start?

The backup cooling water supply to the is NOT available. Assume NO operator actions.

A. control air compressors ONLY B. Unit 1 and 2 RBCCW heat exchangers ONLY C. control air compressors and the Unit 3 RBCCW heat exchanger ONLY D. control air compressors and all three units RBCCW heat exchangers

QUESTION 54 Given the following conditions:

Unit 2 is operating at 20% power with the following indications on Panel 9-5:

CR0 CONTROL SbVrrcH Which ONE of the following completes the statements below?

Using ONLY the CRD CONTROL SWITCH (2-HS-85-48) the operator may withdraw control rods by (1).

If a control rod is withdrawn one notch past its RWM group withdraw limit, the BLUE Rod Out Permit light will (2).

A. (1) single notch ONLY (2) remain illuminated B. (1) single notch ONLY (2) extinguish C. (1) single notch OR continuous rod withdrawal (2) remain illuminated D. (1) single notch OR continuous rod withdrawal (2) extinguish

QUESTION 55 Given the following conditions:

  • A Unit 3 startup is in progress and power is 15%
  • The next control rod in the sequence is 30-47; however the operator incorrectly selects rod 46-31, which is also in the currently latched Rod Group
  • Continuous withdraw is attempted Which ONE of the following completes the statements below?

The control rod will withdraw (1).

In accordance with Tech Spec 3.1.6, Rod Pattern Control, an action (2) required.

A. (1) ONLY one notch (2) is NOT B. (1) ONLY one notch (2) is C. (1) continuously (2) is D. (1) continuously (2) is NOT

QUESTION 56 Which ONE of the following is the power supply to the full core display rod position indications?

A. ICS, Panel 2-LPNL-925-532 B. Unit Preferred, Panel 2-9-9 Cabinet 6 C. Plant Preferred, Panel 2-9-9 Cabinet 4 D. Unit Non-Preferred, Panel 2-9-9 Cabinet 5

QUESTION 57 Given the following conditions:

  • Unit 2 is operating at 100% power
  • 2-PI-3-54, Wide Range Pressure indicates 1045 psig
  • 2-PI-3-61, Wide Range Pressure indicates 966 psig
  • 2-PI-3-207, Wide Range Pressure indicates 1020 psig Which ONE of the following is the reactor pressure used by the Feedwater Level Control System (FWLCS)?

A. 1010.3 psig B. 1020.0 psig C. 1032.5 psig D. 1035.Opsig

QUESTION 58 Unit 2 scrammed due to a small LOCA and the following occurred:

  • RPV Water Level dropped to (-)45 inches
  • Drywell Pressure reached 12.5 psig
  • RHR Loop I was placed in Suppression Chamber and Drywell Sprays The following conditions now currently exist:
  • RPV Level is (+)20 inches and slowly rising
  • RPV Pressure is 500 psig slowly lowering
  • Drywell Pressure is 1.82 psig
  • Suppression Pool Temperature and is 93°F and steady Which ONE of the following completes the statements?

The RHR Loop I Suppression Chamber Spray Valves, 2-FCV-74-57 and 2-FCV-74-58 (1).

RHR Loop I _(2) be simultaneously operated in Suppression Chamber Spray and Suppression Pool Cooling mode at this time.

A. (1) have automatically shut (2) may B. (I) have automatically shut (2) may NOT C. (1) remain open (2) may D. (1) remain open (2) may NOT

QUESTION 59 Given the following conditions:

  • Unit 3 Mode Switch is in REFUEL
  • The Refueling Bridge operator grappled a fuel bundle, raised the grapple, AND commenced moving the bundle towards the core Which ONE of the following completes the statement below?

As the Refueling Bridge moves towards the core, a control rod withdrawal block (1)be generated, and the bridge will _(2).

A. (l)will (2) continue over the core B. (l)willNOT (2) continue over the core C. (l)will (2) stop before it reaches the core D. (1) will NOT (2) stop before it reaches the core

QUESTION 60 Given the following conditions:

  • Unit 1 has automatically scrammed
  • Reactor power is 4% RTP
  • RPV level is being maintained at 25 inches by the feedwater system
  • Suppression Pool temperature is 910 F and rising slowly
  • EOI C-5, LevellPower Control has been entered Which ONE of the following completes the statements below?

[Consider each statement separately]

For the conditions stated above, EOI C-5, Level/Power Control, (1) stopping and preventing injection to the RPV.

The purpose of deliberately lowering RPV water level in EOI C-5, Level/Power Control, is to (2)_.

A. (1) requires (2) maximize boron concentration B. (1)requires (2) minimize core inlet subcooling C. (1) does NOT require (2) maximize boron concentration D. (1) does NOT require (2) minimize core inlet subcooling

QUESTION 61 Given the following conditions:

  • All three units are operating at 100% power
  • CHARCOAL BED GAS REHTR OUTL DEW PT TEMP HIGH, (Panel 9-53, window 27) is in alarm Which one of the following identifies:

(I) a component malfunction that can cause this alarm, and (2) an operational implication if no corrective action is taken?

A. (1) Offgas Preheater (2) Main stack release rate rises B. (1) Offgas Preheater (2) Offgas piping hydrogen explosion C. () Cooler Condenser (2) Main stack release rate rises D. (1) Cooler Condenser (2) Offgas piping hydrogen explosion

QUESTION 62 Which ONE of the following completes the statements below?

The Wide Range Gaseous Effluent Radiation Monitor (WRGERM), O-RM-90-306, is powered from (1).

The Stack-Gas Radiation Monitor detectors (RM-90-l47 & 148) are powered from (2).

A. (1) 25OVDC Battery Board 2 (2) 48VDC Annunciator Battery System B. (1) 25OVDC Battery Board 2 (2) +/-24VDC Neutron Monitoring Battery System C. (1) 25OVDC Battery Board 1 (2) 48VDC Annunciator Battery System D. (1) 25OVDC Battery Board 1 (2) +/-24VDC Neutron Monitoring Battery System

QUESTION 63 Given the following conditions:

  • Unit 2 is operating at 90%
  • Due to a dP instrument malfunction, the 2-PDIC-064-0002, Reactor Zone dP Controller, incorrectly senses Reactor Building dP is (-) 0.5 H 0

2 Which ONE of the following completes the statements below?

[Consider each statement separately]

The controller will cause actual Unit 2 Reactor Building pressure, as compared to outside, to

_( 1).

An EOI-3 entry condition is Secondary Containment dP at or above (2).

A. (1) rise (2) (-) 0.17 H0 2

B. (1) lower (2) (-) 0.25 HO 2

C. (l)rise (2) (-) 0.25 H0 2

D. (1) lower (2) (-) 0.17 H0 2

QUESTION 64 Given the following plant conditions:

  • RX ZONE EXH RADIATION MONITOR DNSC (Panel 9-3A window 35) is in alarm
  • Reactor Zone Exh CH A Rad Mon, 1-RM-90-142A is reading 1.0 XE 1 mr/hr
  • Reactor Zone Exh CH A Rad Mon, l-RM-90-143A is reading 9.3 X E mr/hr
  • Reactor Zone Exh CH B Rad Mon. l-RM-90-142B is reading 7.3 X E 1 mr/hr
  • Reactor Zone Exh CH B Rad Mon, l-RM-90-143B is reading 9.3 X E mr/hr
  • CONT RM ISOL RAD MONITOR DNSCL OR INOP, (Panel 9-6B window 10) is in alarm
  • 0-RM-90-259A, CREVs Rad Mon is reading 30 cpm above background

System response?

A. BOTH CREV units will automatically start immediately B. The Selected CREV unit will automatically start after a time delay. When Control Bay Ventilation is restarted CREV will automatically stop C. The Selected CREV unit will automatically start after a time delay. The Standby CREV unit will ONLY start if the selected CREV unit fails to develop sufficient flow D. NEITHER CREV unit will automatically start under these conditions

QUESTION 65 Which ONE of the following describes the piping configuration for the RWCU system return flow back to the reactor?

A. Units 2 and 3 can return via A or B Fcedwater spargers B. Units 1 and 2 can return via A or B Feedwater spargers C. ONLY Unit 3 can return via A or B Feedwater spargers D. ONLY Unit 1 can return via the A or B Feedwater spargers

QUESTION 66 Which ONE of the following completes the statement below?

The Traversing In-Core Probe System (TIPS) probes are _(1)_ and are used to calibrate the

_(2)_.

A. (1) gamma sensitive ion chambers (2) source range and intermediate range monitors (SRMs/IRMs)

B. (1) fission chambers (2) local power range monitors (LPRMs)

C. (1) fission chambers (2) source range and intermediate range monitors (SRMs/LRMs)

D. (1) gamma sensitive ion chambers (2) local power range monitors (LPRMs)

QUESTION 67 Given the following conditions:

  • Unit 3 was at 100% Reactor Power
  • An event occurred and the operators are performing actions of EOI C-2, EMERGENCY DEPRES SURIZATION Which ONE of the following completes the statements below?

A Wide Range RPV Pressure Indicator (1)_ located at Panel 3-9-3.

The SRVs will begin to close when the Wide Range RPV Pressure Indicator is (2).

A. (l)is (2) 0 psig B. (l)isNOT (2) 50 psig C. (l)isNOT (2) 0 psig D. (1)is (2) 50 psig

QUESTION 68 In accordance with O-GOI-100-3C, Fuel Movement Operations During Refueling, which ONE of the following completes the statements below?

The Fuel Pool Cooling System is only required to be in service to maintain fuel pool water within specifications listed in NPG-SPP-05.3, Chemistry Control, and water temperature less than (1) but greater than 72° F.

RPV water level shall be (2)_feet above the top of the RPV flange during movement of fuel assemblies or the handling of Control Rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

A. (1) 100°F (2)>21.5 B. (1) 125°F (2) >21.5 C. (1) 100°F (2)?22.0 D. (1) 125°F (2)22.0

QUESTION 69 The operating crew is implementing a clearance on the component shown below.

24516143 PURGE AIR Which ONE of the following completes the statements below?

The solenoid is shown (1).

The flow control valve fails (2).

A. (1) energized (2) closed B. (1) energized (2) open C. (1) de-energized (2) open D. (1) dc-energized (2) closed

QUESTION 70 Which ONE of the following completes the statement below in accordance with the bases for Tech Spec 2.1.1, Reactor Core Safety Limits?

The (1) ensures that during normal operation and during abnormal operational transients,

_(2)_.

A. (1) MCPR safety limit (2) at least 99.9% of the fuel rods in the core do not experience transition boiling B. (1) APLHGR safety limit (2) cladding oxidation does not exceed 0.17 percent of the total cladding thickness C. (1) APLHGR safety limit (2) at least 99.9% of the fuel rods in the core do not experience transition boiling D. (1) MCPR safety limit (2) cladding oxidation does not exceed 0.17 percent of the total cladding thickness

QUESTION R071 Which ONE of the following completes the statement below in accordance with Tech Spec 3.1.3, Control Rod Operability?

In accordance with Tech Spec 3.1.3, Condition A, if one withdrawn control rod is stuck, then A. immediately verify separation criteria are met B. Disarm the adjacent control rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Declare the control rod slow within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. Immediately insert and disarm adjacent control rods

QUESTION 72 In accordance with 2-GOI-200-2, Primary Containment Initial Entry and Closeout, entering the drywell, with the primary system at or near rated operating temperature and pressure, requires permission from which ONE of the following?

A. Plant Manager B. Site Vice President C. Radiation Protection Manager D. Operations Manager

QUESTION R073 The Unit 3 is operating at 50%.

Which ONE of the following completes both statements below in accordance with the Precautions and Limitations of 3-01-4, Hydrogen Water Chemistry System?

The MAXIMUM H 2 injection rate allowed is _(l)_.

Placing HWC System in service at higher power levels can result in _(2).

A. (l)25scfm (2) MAIN STEAM LINE RADIATION HIGH annunciator alarming on Panel 3-9f, window 7 6 -Z -/3

@ j(:!

57 B. (l)l2scfm (2) MAIN STEAM LINE RADIATION HIGH annunciator alarming on Panel 3-9 window 7 4

C. (l)25scfm (2) HIGH OFFGAS % H 2 TRAiN A(B) annunciator, Panel 3-53, window 3 (13)

D. (1) 12 scfm (2) HIGH OFFGAS % H 2 TRAIN A(B) annunciator, Panel 3-53, window 3 (13)

QUESTION RO 74 Given the following conditions:

  • The Unit 1 reactor has automatically scrammed
  • Reactor power 3%
  • Reactor water level (+)10 inches (slowly rising, lowest level observed was (-)25 inches)
  • Reactor pressure 1047 psig
  • Suppression Pool Level 16 feet
  • Suppression Pool Temperature 94° F and slowly rising
  • Drywell temperature is 140° F and slowly rising Which ONE of the following completes the statements below?

The Crew 1)_ required to enter C-5, LEVEL/POWER CONTROL.

The OATC j2)_ required to trip the Recirc Pumps.

A. (l)isNOT (2) is B. (1) is (2) is NOT C. (1)isNOT (2) is NOT D. (1)is (2) is

QUESTION 75 Given the following conditions:

  • Unit 2 is in MODE 4, and Shutdown Cooling has been lost Which one of the following completes the statements below In accordance with 2-AOI 1, Loss of Shutdown Cooling?

RWCU _(l) is required to be maximized.

Prior to exceeding 212° F moderator temperature, the preferred mitigation strategy is (2).

A. (1) blowdown flow to the condenser (2) to establish a reactor vessel vent path to the condenser B. (1) return flow to the vessel (2) open SRVs to the Suppression Pool C. (1) blowdown flow to the condenser (2) open SRVs to the Suppression Pool D. (1) return flow to the vessel (2) to establish a reactor vessel vent path to the condenser

RO Reference Table of Contents

13. EQI Curve 2 NPSH Limits
29. 2-SR-3.4.9.1 (1) Table 2

-bLN IMThNUIA-i (Ps Rev. 12 Page 6 of 6 ATTACHMENT 1 NPSH MONITORING Adequate NPSH is assured by maintaining pump flow rates below the curve for the applicable Suppression Chamber pressure For Suppression Chamber pressures between the values on the curves extrapolation must be used.

CURVE 2 RHR NPSH LIMITS 245 235 15 PSIG SAFE 225 10 PSIG SAFE 215 -__

SPSGSAFE

& 205 195

- 0PSG SJ 18 175 165 155 145 $ I I I I I I II I I I I II 500 2500 4500 6500 8500 10500 12000 RHR PUMP FLOW (GPM) SUPPR CHMBR PRESS Other indications of inadequate NPSH are:

  • Suppression pool level below 10.0 ft
  • System flowrate decreastng with constant valve position
  • System flowrate or discharge pressure less than expected for present system conditions
  • Pump discharge pressure lower than expected or fluctuating excessively
  • Pump motor amps lower than expected or fluctuating excessively
  • Pump suction pressure low (local indication)

LAST PAGE

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