ML110240253
| ML110240253 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/24/2011 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| References | |
| 50-324/10-302, 50-325/10-302 | |
| Download: ML110240253 (76) | |
Text
LIST OF REFERENCES FOR RO WRITTEN EXAM
- 1. Steam Tables 2.
OEOP-O1.-UG, ATTACHMENT 5, FIGURE 6, RHR NPSH Limit
OEOP-O1-UG, Attachment 5, Figure 1, Drywell Spray Initiation Limit
Percent speed 50%
Generator voltage 1.9 kV Generator power 0.45 MW Which one of the following describes the expected generator voltage and power if the percent speed is raised to 100%?
Generator voltage will be (1) kV and Generator power will be (2)
MW.
A.
(1) 3.8 (2) 0.9 B.
(1) 3.8 (2) 3.6 C. (1) 7.6 (2) 0.9 D. (1) 7.6 (2) 3.6 Page:
1
- 2. Which one of the following identifies the power supply to the 1-El 1-FO15A, Inboard Injection Valve?
A.E5 B.
E6 C.E7 D.
E8 Page: 2
- 3. Which one of the following identifies the Unit Two RHR actuation Logic A power supply?
A.
125 VDC Panel 3A B.
125 VDC Panel 3B C. 125 VDC Panel 4A D. 125 VDC Panel 4B Page: 3
- 4. Which one of the following choices completes the statement below concerning the impact of a failure of the breakdown orifice in the RWCU reject line while performing a reject to radwaste?
The (1) operated (2) will auto close to prevent over-pressurization of the radwaste piping.
A.
(1) air (2) 2-G31-F033, RWCU Reject Flow Control Vlv, B.
(1) motor (2) 2-G31-F033, RWCU Reject Flow Control Vlv, C. (1) air (2) 2-G31-F035, Reject To Radwaste Vlv, D. (1) motor (2) 2-G31-F035, Reject To Radwaste Vlv, Page: 4
- 5. RHR Loop B and RHR SW Loop B have been placed in the Shutdown Cooling Mode of operation with the following pump alignment:
RHR Pump B Running RHRPumpD STBY RHR SW Pump B Running The following alarms are received:
RHR SYS fACT! VA TED RHR SYS I/ACT! VA TED Then reactor water level indication lowered to 150 inches.
Which one of the following completes the statement below concerning the status of RHR Loop B?
RHR Pump B (1) and the SUCTION valves (2) re-aligned to the suppression pool for injection to the reactor vessel.
A.
(1) has tripped (2) must be manually B.
(1) has tripped (2) have automatically C. (1) continues to run (2) must be manually D.
(1) continues to run (2) have automatically Page:
5
- 6. HPCI has been placed in the pressure control mode of operation following a Group 1 isolation with the flow controller in Automatic.
Which one of the following is a CAUTION the operator must observe while throttling the 2-E41-F008, Bypass To CST Valve, lAW 2OP-19, High Pressure Coolant Injection System Operating Procedure?
Throttling the 2-E41 -F008 (1) too far will result in (2)
A.
(1) closed (2) an overspeed trip B.
(1) closed (2) operation below 2100 RPM C. (1) open (2) an overspeed trip D. (1) open (2) operation below 2100 RPM Page; 6
- 7. During a transient, HPCI initiated on low reactor level then tripped on high reactor level with the following plant conditions present:
Reactor water level 180 inches, steady HPCI Initiation Signal/Reset white light LIT HPCI High Water Level Signal Reset white light LIT HPCI TURB TRIP alarm Sealed in HPCI TIJRB TRIP SQL ENER alarm Sealed in Which one of the following completes the statements below under the above conditions?
If drywell pressure rises to 3.0 psig, the HPCI turbine trip will (1) reset.
If reactor water level then drops to 96 inches, HPCI will inject (2)
A.
(1) auto (2) with NO operator actions B.
(1) auto (2) ONLY if the injection valve is manually opened C.
(1) NOT auto (2) with NO operator actions D. (1) NOT auto (2) ONLY if the injection valve is manually opened Page: 7
- 8. CS Pump 1A is running for surveillance testing when the CS Pump 1A normal control power fuses blow inside its 4KV breaker compartment.
A Loss of Off-Site Power then occurs.
Which one of the following choices completes the statement belOw?
DG1 (1) auto tie onto El because the CS Pump 1A (2)
A.
(1) will (2) alternate control power auto transfers B.
(1) will (2) breaker will auto trip open C. (l)will not (2) breaker fails to trip open D. (l)will not (2) alternate control power must be manually transferred Page: 8
- 9. Unit One is in an ATWS with a spurious Group I signal and the following plant conditions:
Control Rods 97 control rods inserted Reactor pressure band 800 to 1000 psig SLC system Injecting with the tank at 42%.
All IRMs Indicating on Range 6 and 7 Based on the above conditions, which one of the following will cause the reactor to go critical again?
A.
Re-opening of the MSIVs.
B.
Placing RCIC in service for level control.
C. Placing HPCI in service for pressure control.
D. ADS actuation with low pressure ECCS injection.
Page: 9
- 10. Which one of the following completes the statements below?
The Standby Liquid Control (SLC) storage tank level instrument receives pneumatics from the (1)
Airsystem.
Loss of air will cause tank level to indicate (2) than actual level.
A.
(1) Service (2) lower B.
(1) Service (2) higher C. (1) Instrument (2) lower D.
(1) Instrument (2) higher Page: 10
11.
v1 Which one of the following completes the statements below if power to RPS Bus B is lost with the above actual indicated condition (blown fuse) present on Panel P603 (RTGB) while Unit Two is operating at 100% power?
Loss of RPS Bus B will directly cause (1) of the Control Rods to Scram.
If this condition remains, a full reactor Scram will occur, with annunciator (2) providing the FIRST indication of the cause.
A.
(1) 1/4 (one quarter)
(1) 1/4 (one quarter)
(2) SDV HI-HI LEVEL RPS TRIP C. (1) 1/2 (one half)
(2) ECCS DIV/I RPT/ARI TR D. (1) 112 (one half)
(2) SDV HI-HI LEVEL RPS TRIP Page:
11
- 12. Which one of the following identifies how the Reactor Manual Control System (RMCS) will be affected by a total loss of the Uninterruptible Power Supply (UPS)?
Control rods can be inserted by Scram:
A.
ONLY.
B. or using Notch In switch ONLY.
C. or using Emergency Rod In switch ONLY.
D. or using Notch In switch, or Emergency Rod In switch.
Page:
12
- 13. Which one of following describes the impact that a loss of RPS Bus A will have on the Unit One Rod Block Monitoring (RBM) System?
RBM Channel A generates a (1) self test fault.
The annunciator procedure (2) the steps to bypass the RBM, if required.
A.
(1) critical (2) does NOT contain B.
(1) critical (2) contains C. (1) non-critical (2) does NOT contain D. (1) non-critical (2) contains Page: 13
- 14. A plant startup is in progress when the high voltage power supply for IRM G failed low.
All IRMs are on range 1. (Mode switch is in Startup)
Which one of the following choices completes the statements below?
The expected plant response is a (1)
The action required lAW the annunciator procedure(s) is to place the (2)
A.
(1) rod block ONLY (2) joystick on P603 for IRM G to Bypass B.
(1) rod block ONLY (2) operate switch on the IRM G drawer to STANDBY C. (1) rod block with a half scram (2) joystick on P603 for IRM G to Bypass D. (1) rod block with a half scram (2) operate switch on the IRM G drawer to STANDBY Page: 14.
- 15. Unit Two is in Mode 5 with the RPS shorting links removed.
Consider the following SRM events (individually):
- 1. SRM channel A fails full upscale
- 2. SRM channel B drawer switch is placed to Standby
- 3. SRM channel C loses power to the drawer Which one of the following identifies the event(s) that will cause a full reactor scram?
A.
1 ONLY B.
2 ONLY C. lor3 D. 2or3 Page:
15
- 16. Which one of the following completes the statement below regarding the Power Range Neutron Monitoring System Operability?
bach APRM must have a minimum of (1)
Operable LPRMs, with at least 3 Operable LPRMs per axial level to ensure that the APRM wifl provide an accurate representation of (2) power.
A.
(1) 17 (2) axial relative B.
(1) 17 (2) core wide average C.
(1) 18 (2) axial relative D. (1) 18 (2) core wide average Page:
16
- 17. Unit Two reactor pressure is 170 psig when the CST is ruptured causing CST Level to drop to two feet.
Which one of the following choices completes the statement below?
In response to this event, the Torus Suction Valves, 2-E51-F029 and 2-E51-F031, will (1) and the CST Suction Valve, 2-E51-F010, will (2)
A.
(1) remain closed (2) auto close B.
(1) remain closed (2) remain open C. (1) auto open (2) auto close D. (1) auto open (2) remain open Page: 17
- 18. How will the operation of SRVs be affected due to an actual Core Spray LOCA signal?
Backup Nitrogen aligns to supply pneumatics to (1)
If the Backup Nitrogen System fails, (2) are equipped with accumulators A.
(1) ALL SRVs (2) ADS SRVs ONLY C. (1) ADS SRVs ONLY (2) ALL SRVs D. (1) ADS SRVs ONLY (2) ADS SRVs ONLY Page:
18
- 19. Which one of the following completes the statement below regarding Unit One and Unit Two Drywell Cooler start logic?
The Drywell Cooling fans that automatically start due to its associated discharge damper opening are (1) and (2)
A.
(1) ALL Unit One Cooling Fans (2) ALL Unit Two Cooling Fans B.
(1) ALL Unit One Cooling Fans (2) 2B Cooling fan ONLY C.
(1) lB Cooling fan ONLY (2) ALL Unit Two Cooling Fans D. (1) lB Cooling fan ONLY (2) 2B Cooling fan ONLY Page:
19
- 20. Unit One is in Shutdown Cooling using RHR Loop B.
A transient occurs with the following plant conditions:
Reactor water level lowers to 170 inches Reactor pressure 135 psig and rising Which one of the following identifies the response, if any, of the RHR system?
A.
ONLY RHR Inboard Injection Isolation Valve (Ell-FO15B) receives a close signal.
B.
ONLY RHR SDC Suction Isolation Valves (E1l-F008 & E1l-F009) receive a close signal.
C. RHR Inboard Injection Isolation Valve (El lF0l5B) and RHR SDC Suction Isolation Valves (Ell-F008 & E1lF009) all remain open.
D. RHR Inboard Injection Isolation Valve (El1-FO15B) and RHR SDC Suction Isolation Valves (El 1-F008 & El l-F009) all receive a close signal.
Page: 20
Reactor water level Reactor pressure Suppression Pool temperature Drywell Average Air temperature Drywell pressure Suppression Chamber pressure Torus level 55 inches and rising with Core Spray 150 psig 220° F 289° F 12 psig 10.5 psig
-43 inches (Reference Provided)
Which one of the following identifies the maximum RHR flow (per pump) that can be established for Drywell Sprays?
A. 4000 gpm B. 6000 gpm C. 9000 gpm D. llSOOgpm Page: 21
- 22. Which one of the following completes the statement below?
2B RHR Pump is powered from Bus (1) which under normal conditions is powered from BOP Bus (2)
A.
(1) E2 (2) 1C B.
(1) E2 (2)1D C. (1) E4 (2) 2C D. (1) E4 (2) 2D Page: 22
- 23. Which one of the following completes the statement below?
A loss of power to the Unit Two Refuel Bridge from MCC (1) will cause the (2) during fuel loading activities.
A.
(1) 2XG (2) bridge brakes to engage ONLY B.
(1) 2XG (2) bridge brakes to engage and the main grapple to close C. (1) 2XDA (2) bridge brakes to engage ONLY D. (1) 2XDA (2) bridge brakes to engage and the main grapple to close Page: 23
- 24. Which one of the following describes the effect that a loss of MCC 1XDB will have on the Unit One Safety Relief Valves (SRV5), if needed for pressure control operations from the RSDP?
SRVs B, E, and (1) will lose (2)
A.
(1)
F (2) position indication ONLY B.
(1)
F (2) ALL control and indications C.(1)G (2) position indication ONLY D. (1) G (2) ALL control and indications Page: 24
- 25. Unit One has just received annunciator AUTO DEPRESS CONTROL PWR FAILURE.
Subsequent investigation reveals no light indication for any ADS!SRV at panel P601.
Based on these indications which one of the following is the cause and how is ADS!SRV operation affected?
A.
Loss of DC power supply from panel 3B ONLY.
SRV pressure relief ONLY will function.
B.
Loss of DC power supply from panel 3B ONLY.
ADS logic and SRV pressure relief will function.
C. Loss of DC power supply from panels 3A and 3B.
SRV pressure relief ONLY will function.
D. Loss of DC power supply from panels 3A and 3B.
ADS logic and SRV pressure relief will function.
Page: 25
- 26. Unit Two is in Mode 4, placing RWCU in service after maintenance.
Which one of the following Feedwater System valves, if stuck in the CLOSED position, will prevent RWCU return flow to the vessel?
A.
B21-F032A, Feedwater Isol Vlv B.
B21-F032B, Feedwater Isol Vlv C. B21-FO1OA, Feedwater Line Inlet RPV Check Vlv D. B21-FO1OB, Feedwater Line Inlet RPV Check VIv Page: 26
Which one of the following actions is required lAW OAOP-23.O, Condensate/Feedwater System Failure, based upon the above indications?
A. Reduce reactor power to stabilize level.
B. Place 2A RFPT Speed Controller in Manual.
C. Place 2B RFPT Speed Controller in Manual.
D. Place the Master Level Controller in Manual.
- 27. Unit Two is operating at rated power when the following plant conditions are observed:
REACTOR WATER LEVEL HIGH/LOW In alarm E
I F
[
- ;LwEi J
I Page: 27
- 28. The following are the highest indicated reactor water level after a scram:
Reactor Water Level Indication C32-R606-N004A 205 inches C32-R606-NOO4B 207 inches C32-R606-NOO4C 208 inches Which one of the following choices completes the statement below?
The RFP trip logic utilizes a (1) out of 3 logic and (2)
RFP A & B High Level Trip/Reset lights are expected to be illuminated.
A. (1)2 (2) ONLY the B and C B.
(1) 2 (2) the A, B, and C C.(1)1 (2) ONLY the B and C D. (1) 1 (2) the A, B and C Page: 28
- 29. Which one of the following identifies the impact of starting a SBGT Train on Reactor Building pressure and the reason for this response?
Reactor Building pressure will initially become (1) negative and then returns to the initial value due to repositioning of the Reactor Building (2)
Fan vortex dampers.
A.
(1) less (2) Exhaust B.
(1) less (2) Supply C. (1) more (2) Exhaust D.
(1) more (2) Supply Page: 29
- 30. Which one of the following identifies the source of power to Caswell Beach Bus A?
A.
SAT B.
Common A C. Southport Feeder D. 230 kV Transformer Bus Page: 30
- 31. The indications and status of the UPS system at the primary and standby inverters are as follows:
Primary Inverter Standby lnverter Load on UPS light Off Off Load on Inverter light Off On Load on Alternate light On Off Alt Source Failure light Off Off Manual Bypass switch Norm Bypass Test Which one of the following is the current status of UPS system loads?
A.
De-energized.
B.
Energized from the MCC 2CA.
C. Energized from the MCC 2CB.
D. Energized from the standby inverter.
Page: 31
- 32. A LOCA with a loss of off-site power occurs on Unit Two with DG3 under clearance.
Which one of the following identifies the status of the Unit Two 125!250V DC Electrical Distribution System?
Div I 125V DC Battery Chargers:
A. and Div II 125V DC Battery Chargers will all be energized.
B. and Div II 125V DC Battery Chargers will all be deenergized.
C. will be energized but Div II 125V DC Battery Chargers will be deenergized.
D. will be deenergized but Div II 125V DC Battery Chargers will be energized.
Page: 32
- 33. During a monthly load test of DG4, the following sequence of events occUrred within a 25 second time frame:
Event 0 Sychroscope is rotating slow in the FAST direction.
Event 1 Operator closes the generator output breaker with the synchroscope at the 12 oclock position.
Event 2 The Voltage Adjust Rheostat is taken to the Raise position.
Event 3 DG4 trips due to a generator lockout relay actuation.
Which one of the following identifies the cause of the generator lockout due to the Operator actions above?
A. Overexcitation B. Reverse power C. Phase overcurrent D. Differential overcurrent Page: 33
- 34. Which one of the following choices completes the statement below with Unit One operating at rated power?
The normal temperature of the in-service offgas catalytic recombiner outlet is approximately (1)
°F and recombiner outlet temperature (2) dependent on hydrogen concentration.
A. (1) 300 (2) is B. (1) 300 (2) is not C. (1) 600 (2) is D. (1) 600 (2) is not Page: 34
- 35. The power supply to Unit One Reactor Building Exhaust Radiation Monitor A (Dl 2-RM-K609A) is (1) and a failure of this power supply will cause (2)
A. (1) RPSA (2) RB HVAC Isolation ONLY B.
(1) RPSA (2) RB HVAC Isolation and SBGT start C. (1) 12OVAC distribution panel 1A (2) RB HVAC Isolation ONLY D. (1) l2OV AC distribution panel 1A (2) RB HVAC Isolation and SBGT start Page: 35
- 36. Control Building ventilation was manually aligned for the radiation mode with the controls positioned as follows:
Which one of the following completes the statement below if an actual CREV auto initiation signal is received with the above system alignment present?
CB Emerg Recirc Fan A will:
A.
immediately start.
B. start ten (10) seconds later.
C. remain off unless CREV Fan B trips.
D. remain off even if CREV Fan B trips.
Page: 36
- 37. The 2A Reactor Recirculation pump trips while Unit Two is operating at rated power.
Which one of the following identifies how RPV water level will initially respond and the reason for this response?
Indicated RPV water level will (1) due to the displacement of water by increased steam voiding (2)
A.
(1) increase (2) in the downcomer region B.
(1) increase (2) inside the shroud C. (1) decrease (2) in the downcomer region D. (1) decrease (2) inside the shroud Page: 37
- 38. Unit Two is operating at rated power when a full / partial Primary Containment isolation signal is received to Groups 2, 3, 6, 8, and 10.
Which one of the following identifies the event which caused these isolations?
A.
Bus E4 de-energizing B. RPS Bus A de-energizing C. Drywell pressure rising to 3.0 psig D. RPV water level lowering to 95 inches Page: 38
- 39. Unit One is operating at rated power when the normal DC control power supply to Buses E2 and E6 is lost.
Which one of the following describes the effect this power loss will have on the ability of the breakers on Bus E2 and Bus E6 to trip on a fault overcurrent condition?
(Assume no operator action)
A.
ONLY the breakers on Bus E2 will trip.
B.
ONLY the breakers on Bus E6 will trip.
C. Breakers on BOTH Bus E2 and Bus E6 will trip.
D. Breakers on BOTH Bus E2 and Bus E6 will fail to trip.
Page: 39
- 40. Unit Two is operating at 23% reactor power with a shutdown in progress when the Main Turbine trips due to Generator Differential Lockout.
Which one of the following completes the statements below?
Final Feedwater Temperature will (1) the Main Turbine trip and at this power level the reactor (2) automatically Scram.
A. (1)lowerdueto (2) will B. (1)lowerdueto (2) will NOT C. (1) stay the same regardless of (2) will D. (1) stay the same regardless of (2) will NOT Page: 40
- 41. A High DW pressure Scram on Unit Two has resulted in all control rods fully inserted with following exceptions:
Control Rod Position 26-31 02 26-23 02 22-35 02 22-27 02 18-23 02 18-39 02 30-23 02 30-35 02 34-31 02 Which one of the following choices completes the statement below?.
The reactor (1) remain shutdown under all conditions without boron.
The operator must insert the control rods (2) lAW LEP-02.
A. (1) will (2) by driving rods using RMCS B. (1)will (2) by placing the individual scram test switches to the Scram position C. (1)will NOT (2) by driving rods using RMCS D. (1)will NOT (2) by placing the individual scram test switches to the Scram position Page: 41
- 42. Following a reactor scram on Unit One, plant conditions are:
Reactor water level 150 inches, rising Reactor pressure 700 psig, steady Drywell ref leg temp 195°F (Reference provided)
Which one of the following identifies the reactor water level at which tbe MSIVs must be closed lAW the RSP?
A. 230 inches B. 240 inches C. 250 inches D. 260 inches Page: 42
- 43. Unit Two is operating at 60% power when an inadvertent HPCI initiation signal causes HPCI injection to occur.
Which one of the following completes the statements below?
Pressure Averaging Manifold (PAM) pressure will stabilize at a (1) pressure.
Main Turbine Control Valves MS-CV-1, MS-CV-2, (2) throttle to maintain pressure.
A.
(1) lower (2) and MS-CV-3 B.
(1) lower (2) MS-CV-3, and MS-CV-4 C. (1) higher (2) and MS-CV-3 D. (1) higher (2) MS-CV-3, and MS-CV-4 Page: 43
- 44. Which one of the following describes the reason a cooldown is NOT initiated in the pressure leg of [PC prior to Cold Shutdown Boron Weight (CSBW) being injected during an ATWS condition lAW 001-37.5, Level/Power Control Procedure Basis Document?
A. Core reactivity response is unpredictable in a partially borated core.
B.
Initiating a cooldown while injecting boron will prevent the boron from being uniformly mixed.
C. Steaming rates will lower resulting in stagnant core flow which may lead to neutron flux oscillations.
D. To ensure that low pressure injection systems cannot injectinto the vessel and add positive reactivity.
Page: 44
- 45. Which one of the following is the reason for inserting a Scram during the performance of OAOP-32.O, Plant Shutdown From Outside Control Room?
A Scram is inserted prior to (1) to ensure (2)
A.
(1) evacuating the Control Room ONLY (2) the reactor is placed in a hot shutdown condition B.
(1) evacuating the Control Room ONLY (2) control of engineered safeguards systems from a backup control center can be executed C. (1) OR following Control Room evacuation (2) the reactor is placed in a hot shutdown condition D. (1) OR following Control Room evacuation (2) control of engineered safeguards systems from a backup control center can be executed Page: 45
- 46. Unit Two has been operating with CSW Pump 2A in service and 05W Pump 2B in standby.
Which one of the following identifies the 05W pump start limitations that apply lAW 20P-43, Service Water System Operating Procedure if CSW Pump 2A trips?
CSW Pump 2A can be restarted (1)
(if necessary) and CSW Pump 2B is limited to (2) starts in succession.
A.
(1) once (2) two B.
(1) once (2) three 0.
(1) twice (2) two D. (1) twice (2) three Page: 46
- 47. How will the loss of Instrument Air in Radwaste INITIALLY impact the operation of the Condensate Deep Bed Demineralizers (CDD)?
Loss of Instrument Air to in service CDDs will cause the Effluent Flow Control (E) valves to fail (1) and the Bypass (CD-PV-401) valve will fail (2)
A. (1) closed (2) open B. (1) closed (2) as-is C. (1) as-is (2) open D. (1) as-is (2) as-is Page: 47
- 48. During ATWS conditions on Unit Two, the MSIVs inadvertently close during Mode switch positioning to Shutdown.
Three (3) SRVs are currently open stabilizing RPV pressure at 1000 psig.
What percent power is the reactor currently producing?
A.3%
B.6%
C. 18%
D. 48%
Page: 48
- 49. Unit Two is in Cold Shutdown with both Reactor Recirculation pumps shutdown.
Shutdown Cooling (SDC) has been established using RHR Loop B.
Which one of the following completes the statement below for a loss of shutdown cooling under the above conditions lAW OAOP-15.O, Loss of Shutdown Cooling?
RPV Level must be raised to at least (1) inches to establish (2)
A.
(1) 254 (2) natural circulation B.
(1) 254 (2) feed and bleed evolutions C. (1) 200 (2) natural circulation D. (1) 200 (2) feed and bleed evolutions Page: 49
- 50. Which one of the following is a Plant Design Feature credited for minimizing the radiological impact of a Design Bases Refueling Accident lAW the Updated Final Safety Analysis Report (UFSAR)?
A. Control Building Ventilation Radiation Monitoring System auto start of CREV.
B. Reactor Building Ventilation Radiation Monitoring System auto start of SBGT.
C. Refueling Bridge Boundary Zone Control System preventing fuel movements into forbidden areas.
D. Spent Fuel Pool and Cooling System maintaining Spent Fuel Pool level greater than 23 feet over irradiated fuel.
Page: 50
- 51. Following a line break in the drywell, Unit One conditions are:
Drywell pressure 15 psig Drywell temperature 250°F Suppr chamber pressure 13.5 psig Suppr chamber level
-24 inches Which one of the following identifies the reason PCCP directs initiation of drywell spray under these conditions?
Drywell Spray is directed to:
A. prevent operation of suppression chamber to drywell vacuum breakers.
B. redistribute noncondensibles from the suppression chamber to the drywell.
C. lower drywell temperature due to exceeding the drywell design temperature limit.
D. reduce drywell pressure due to the Pressure Suppression Pressure Limit being exceeded.
Page: 51
- 52. Unit One has been operating at rated power for the last 18 months.
A Loss of Off-site Power (LOOP) occurs and will not be restored for 7 days.
Which one of the following identifies the MINIMUM time following this event that is required until reactor pressure can be stabilized by ONLY operating HPCI in pressure control?
A.
5 seconds B.
1 minute C.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D.
5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Page: 52
- 53. Which one of the following indicates the color code displayed by the Safety System Parameter Display System (SPDS) with regards to the Suppression Pool temperature?
When suppression pool temperature is 96°F the color code is:
A. red.
B. green.
C. yellow.
D. white.
Page: 53
- 54. A small steam leak in the Unit One drywell results in the following plant conditions:
Drywell Pressure 5.0 psig Drywell Average Temp.
295°F Drywell Reference Leg Area Temp.
340°F Suppression Chamber Pressure 4.5 psig Suppression Pool Water Level 20 inches Which one of the following completes the statement below?
(Reference Provided)
Operation of drywell spray is prohibited because:
A. Suppression Pool level is too high.
B. air could be introduced into primary containment.
C. the Torus vent pipe has the potential for collapsing.
D. the Suppression Chamber Spray Initiation Pressure Limit is being exceeded.
Page: 54
- 55. Unit One is operating the HPCI system during post maintenance testing when a loss of power occurs to some of the DW Coolers.
The following plant conditions exist:
Drywell Temperature 155°F Suppression Pool Temperature 97°F Suppression Pool Water Level
-32 inches Which one of the following identifies the reason(s) that POOP must be entered?
A.
Drywell Temperature ONLY B. Suppression Pool Temperature ONLY C. Suppression Pool Water Level and Drywell Temperature D. Suppression Pool Water Level and Suppression Pool Temperature Page: 55
- 56. Which one of the following completes the statements below?
If RPV water level lowers below (1)
, LPCI will automatically start.
With RPV pressure at 285 psig, RHR injection flow to the RPV (2) be observed on the P601.
A.
(1) LL3 (2) can B.
(1)
LL3 (2) CANNOT C. (1) LL2 (2) can D. (1)
LL2 (2) CANNOT Page: 56
- 57. Which one of the following is the basis for inserting a manual reactor Scram due to elevated radiation levels lAW 001-37.9, Secondary Containment Control Basis Document?
A. The highest radiation level expected to occur during normal plant operation.
B. The radiation level above which equipment necessary for safe shutdown will fail.
C. The radiation level at which installed radiation monitors reachtheirhi-hi setpoints.
D. The radiation level above which personnel access necessary for safe shutdown will be precluded.
Page: 57
- 58. After restarting Reactor Building HVAC per SEP-04, Reactor Building HVAC Restart Procedure, the operator observes that the SBGT System has initiated and the Reactor Building Vent Supply and Exhaust Isolation Dampers have closed.
Which signal caused this to occur?
A.
Reactor water level dropped below LL2.
B. Process Rx Bldg Vent Rad Hi Hi alarmed.
C. Drywell pressure has increased to 2.5 psig.
D. Off-Gas Vent Pipe Radiation Hi-Hi alarmed.
Page: 58
- 59. Which one of the following completes the statements below?
The Unit Two Reactor Building quipment Drain Tank (RBEDT) overflows to the (1)
The MINIMUM RHR room water level requiring SCCP entry is (2) inches.
A.
(1) North (2) 12 B.
(1) North (2) 6 C. (1) South (2) 12 D. (1) South (2) 6 Page: 59
The following Main Steam Line Flow indications are noted:
Which one of the following identifies the approximate reactor power level Main Steam Line Flow?
A. 25% power B.
18% power C. 6% power D. 4.5% power based on the S
Page: 60
- 61. During an off-site release event the Control Room Area and Control Building Vent Intake Plenum Area Radiation Monitors indicate as follows:
Channel 1-1 (Control Room Area) reading 0.3 mr/hr Channel 1-2 (Control Building Vent Air Intake Plenum) reading 9 mr/hr Channel 1-3 (Control Building Vent Air Intake Plenum) reading 10 mr/hr Which one of the following completes the statement below due to the above conditions?
The CB Washroom Exhaust Fans will be (1) and the Battery Room Vent Fans will be (2)
A.
(1) tripped (2) tripped B.
(1) tripped (2) running C. (1) running (2) tripped D. (1) running (2) running Page: 61
- 62. Unit Two is operating at rated power.
The following annunciators and indications are observed:
AIR COMPR D TRIP Sealed in INST AIR PRESS LOW Sealed in SERVICE AIR PRESS LOW Sealed in Air Compressor 2B Running Instrument Air Header pressure 100 psig The RO enters OAOP-20.0, Pneumatic (Air/Nitrogen) System Failures, and verifies Air Compressor 2B has loaded.
Based on the above conditions, which one of the following automatic action(s) is required to be verified lAW OAOP-20.0?
A. Service Air Dryer Bypass Pressure Control Valve SA-PV-5067 has opened.
B. Service Air Isolation Valves, SA-PV-706-1 & 2 have closed.
C.
Div I Backup N2 Rack Isol Vlv, RNA-SV-5482 has opened.
D. Cross-tie Valve, 2-SA-PV-5071 has closed.
Page: 62
- 63. Which one of the following completes the statements below regarding a CSW pump trip with the Standby CSW pump failing to automatically start with Unit One operating at rated power?
If CSW header pressure remains at 35 psig for (1) seconds, the SW-V3 (SW TO TBCCW HXS OTBD SQL) and SW-V4 (SW TO TBCCW HXS INBD ISOL) close to a throttled position.
The SW-V3 and SW-V4 are reopened (2) lAW OAOP-19, Conventional Service Water System Failure.
A.
(1) 40 (2) ONLY after a reactor Scram is inserted B.
(1) 40 (2) if system pressure is restored by starting the standby CSW pump C. (1) 70 (2) ONLY after a reactor Scram is inserted D. (1) 70 (2) if system pressure is restored by starting the standby 05W pump Page: 63
- 64. A fire in Unit Two Reactor Building causes NRHR room temperature to rise above Maximum Normal Operating Value.
Which one of the following completes the statement below lAW 001-37.9, Secondary Containment Control Procedure Basis Document with fire fighting activities in progress?
If NRHR room water level reaches the Maximum Safe Operating Value, fire suppression (1) required to be isolated and a reactor scram is (2)
A. (1) is (2) required B. (1) is (2) NOT required C. (1) is NOT (2) required D. (1) is NOT (2) NOT required Page: 64
- 65. Unit One is operating at rated power.
The load dispatcher reports degraded grid conditions with the following indications present for the LAST ONE MINUTE:
Generator frequency 59.7 hertz 230 KV Bus 1A voltage 205 KV 230 KV Bus 1 B voltage 205 KV Emergency Bus El voltage 3690 volts Emergency Bus E2 voltage 3685 volts Which one of the following describes:
(1) the impact of the above conditions AND (2) what operator actions are required to mitigate the consequences of the above degraded grid conditions lAW OAOP-22.0, Grid Instability?
A. (1) Main turbine blade damage may occur due to off frequency operation.
(2) Immediately Scram the reactor and trip the main turbine ONLY.
B.
(1) Main turbine blade damage may occur due to off frequency operation.
(2) Open the Emergency Bus Master/Slave breakers and ensure diesel generators start and load.
C. (1) Emergency bus loads may be damaged by degraded voltages.
(2) Immediately Scram the reactor and trip the main turbine ONLY.
D. (1) Emergency bus loads may be damaged by degraded voltages.
(2) Open the Emergency Bus Master/Slave breakers and ensure diesel generators start and load.
Page: 65
- 66. Unit Two is operating with feedwater flow bypassing around the high pressure Feedwater Heaters lAW OGP-13, Increasing Unit Capacity At End Of Core Cycle.
Which one of the following completes the statements below in regards to operating under the above condition?
Reduced feedwater heating (1) the possibility of an instability event.
Prior to reducing reactor power below (2)
, the 2-FW-V1 20, Feedwater Heaters 4 and 5 Bypass Valve is required to be closed.
A.
(1) reduces (2) 40%
B.
(1) reduces (2) 50%
C.
(1) increases (2) 40%
D. (1) increases (2) 50%
Page: 66
- 67. Which one of the following identifies the required operator actions if a single notch withdrawal of a control rod results in a reactor period of 19 seconds lAW OGP-02, Approach To Criticality And Pressurization Of The Reactor?
A. Single notch insert the control rod and wait for period to stabilize at greater than or equal to 100 seconds before continuing.
B. Shutdown the reactor and discontinue reactor startup until an assessment as to the cause/recommendation to prevent recurrence has been made by the Reactor Engineer and approved by the Unit CRS.
C. Insert control rods to achieve a stable period of greater than or equal to 100 seconds and discontinue rod withdrawal until a thorough assessment has been performed by the Reactor Engineer and approved by the Unit CR5.,
D. Fully insert Ten control rods past the step in GP-10 at which the short period was experienced and discontinue rod withdrawal until a thorough assessment has been performed by the Reactor Engineer and approved by the Unit CRS.
Page: 67
- 68. Unit Two is operating at power when the following alarms are received:
RBCCWHEAD TANK LEVEL HI/LO RBCCW PUMP DISCH HEADER PRESS LOW The operator observes that RBCCW Pumps 2A, 2B, and 20 are running and header pressure indicates 50 psig on XU-2 and receives CLEANUP FILT INLET TEMP HI annunciator.
Which one of the following identifies the operator actions that are required lAW OAOP-16.0, RBCCW System Failure?
A. Reduce Recirc Pumps to 10% speed and then insert a manual reactor scram.
B. Place RBCCW Pump 2D in service on Unit Two to restore header pressure.
C. Reduce Core Flow to 47 Mlbs/hr and then insert a manual reactor scram.
D. Remove Fuel Pool Cooling from service to reduce system heat loading.
Page: 68
- 69. Unit heatup and pressurization is being performed per GP-02, Approach to Criticality and Pressurization of the Reactor, with the following plant conditions:
RPV pressure 945 psig Reactor power 8%
Mode Switch START/HOT STBY An EHC system malfunction causes all turbine bypass valves to fail open.
Which one of the following choices completes the statement below?
An automatic Group 1 isolation will occur on A.
Unit One ONLY B. UnitTwo ONLY C. BOTH Unit One AND Unit Two D. NHTHR Unit One NOR Unit Two Page: 69
- 70. Unit Two is operating at rated power when the following annunciator is received:
TURB BLDG VENT HAD HIGH Which one of the following is the required actions for this situation?
Enter AOP-50, Radioactive Spill, High Radiation and Airborne Activity (1)
Unit Two Turbine Bldg Ventilation is required to be placed in (2)
A.
(1) ONLY (2) the recirculation line-up B.
(1) ONLY (2) the once through line-up for monitored flow C. (1) AND RRCP (2) the recirculation line-up D. (1) AND RRCP (2) the once through line-up for monitored flow Page: 70
- 71. A valve lineup is to be performed in an area that has the following conditions:
Area temperature 1150 F Area radiation 40 mr/hr Independent verification of this valve lineup is expected to take 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Which one of the following choices completes the statement below in accordance with OPS-NGGC-1 303, Independent Verification?
Based on the conditions above independent verification of this lineup may A.
NOT be waived B. be waived because of excessive dose ONLY C. be waived because of extreme temperature ONLY D. be waived because of BOTH extreme temperature AND excessive dose Page: 71
- 72. Which one of the following completes the statements below regarding Drywell entry requirements with reactor power at 10% lAW OE&RC-0261, Drywell Entry?
Drywell entry at this power level shall be approved by the (1)
The (2) is responsible for authorizing and controlling access into the drywell.
A.
(1) Manager
- E&RC (2) Shift Manager B.
(1) Manager-E&RC (2) RC Supervisor C. (1) Plant General Manager (2) Shift Manager D. (1) Plant General Manager (2) RC Supervisor Page: 72
- 73. During a Unit One Station Blackout, 0AOP-36.2, Station Blackout, RVCP, and PCCP are being performed.
RVCP directs a cooldown not to exceed 100°F/hour, while OAOP-36.2 directs a cooldown at a rate >100°F/hour.
Which one of the following is the cooldown rate required to be performed on Unit One, and the reason that cooldown rate is approprtate?
A. 100°F/hour. The actions directed by an FOP will always override actions directed by an AOP.
B. 100°F/hour.
Exceeding the Technical Specification cooldown rate limit can only be authorized by the FOP.
C. >100°F/hour. This action is required during Station Blackout to prevent exceeding drywell design temperature.
D. >100°F/hour. This action is required during Station Blackout to prevent exceeding suppression pool heat capacity.
Page: 73
- 74. Which one of the following completes the statement below regarding On-Shift Reactor Operator responsibilities lAW OPS-NGGC-1 000, Fleet Conduct of Operations, during a Site Area Emergency with ALL Emergency Facilities activated?
During an emergency, Reactor Operators are required to (1) and if necessary (2)
A.
(1) report to the Control Room (2) review and concur with Emergency Notification Forms B.
(1) report to the Control Room (2) deviate from procedures (10 CFR 50.54x) with approval from the SM or CRS, to protect the health and safety of the public C.
(1) perform direct orders from the Site Emergency Coordinator (2) review and concur with Emergency Notification Forms D. (1) perform direct orders from the Site Emergency Coordinator (2) deviate from procedures (10 CFR 50.54x) with approval from the SM or CRS, to protect the health and safety of the public Page: 74
- 75. Unit One was operating at rated power when a turbine trip resulted in a reactor scram.
Control rods failed to insert.
Terminate and Prevent actions have been completed. Plant conditions are currently:
RPV water level 125 inches RPV pressure 965 psig Drywell pressure 1.0 psi 9
Suppr pool temp 101°F Reactor power 22%
Bypass valves 31/2 open SRVs Closed Which one of the following identifies the HIGHEST RPV water level that injection from the Feedwater System can be re-established lAW LPC?
A. <90 inches.
B. <60 inches.
C. <TAF.
D. <LL4.
Page: 75