ML17131A200
| ML17131A200 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/11/2017 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML17131A200 (110) | |
See also: IR 05000259/2017301
Text
ES-401 Site-Specific SRO Written Examination Form ES-401-8
Cover Sheet
U. S. Nuclear Regulatory Commission
Site-Specific SRO Written Examination
Applicant Information
Name:
Date: Facility / Unit BFN / U1,2,3
Region: I II III IV Reactor Type: W CE BW GE
Start Time: Finish Time:
Instructions
Use the answer sheets provided to document your answers. Staple this cover sheet on top of the
answer sheets. To pass the examination you must achieve a final grade of at least 80 percent overall,
with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only
exams given alone require a final grade of 80 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the
combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification
All work done on this examination is my own. I have neither given nor received aid.
__________________________________
Applicant's Signature
Results
RO/SRO-Only/Total Examination Values ______ / ______ / ______
Points
Applicant's Score ______ / ______ / ______
Points
Applicant's Grade ______ / ______ / ______
Percent
1
7. Power/Flow map attached to question
15. 2-AOI-74-1 Illustration 1 attached to question
19. EOI curve 3 attached to question
36. ICS IRM screen shoot attached to question
67. EOI-5 NPSH curve 1 and 2 attached to question
76. Unit 2 TS 3.8.1 and TS 3.8.7
77. Unit 2 TRM 3.5.4
78. Unit 2 EOI curve 5
79. Unit 2 TS 3.7.1 and 3.7.2
82. EPIP-1 classification matrix only and NPG-SPP-03.5 Immediate Notification Criteria
87. EPIP-1 (see 82)
88. Unit 2 Tech Spec 3.3.1.1 and Table 3.3.1.1-1 with allowable values redacted.
92. Unit 3 TS 3.6.1.3
93. Unit 1 TS 3.3.1.1 and table 3.3.1.1-1 with allowable values redacted,
ODCM 1/2.1.2 and table 1.1-2
98. Unit 2 TS 3.3.7.1 and table 3.3.7.1-1 with allowable values redacted and TS 3.7.3
Q1
Which one of the following completes the statement below?
The EOI-2, Primary Containment Control, Entry Condition set point for Low Suppression
Pool Level is _______ inches.
A. (-) 5.50
B. (-) 6.00
C. (-) 6.25
D. (-) 7.25
2
Q2
HPCI has initiated on an invalid signal.
Which one of the following completes both statements with respect to high reactor water
level and HPCI?
The HPCI high reactor water level trip set point is __ (1) __ inches.
In accordance with ODM 4.20, Strategies for Successful Transient Mitigation, if HPCI has
a sealed in high water level trip when a high Drywell Pressure signal is received, then __
(2) __ the high water level trip.
A. (1) +51
(2) reset
B. (1) +51
(2) do NOT reset
C. (1) +55
(2) reset
D. (1) +55
(2) do NOT reset
3
Q3
Unit 1 entered 1-AOI-1-1, Relief Valve Stuck Open, due to a partially open Main Steam
Relief Valve.
The crew is placing Suppression Pool Cooling in service in accordance with 1-OI-74,
Residual Heat Removal System.
Which one of the following completes both statements below?
In accordance with 1-OI-74, it is preferable to operate __ (1) __ while in Suppression Pool
Cooling.
In accordance with 1-EOI-2, when Suppression Pool Temperature exceeds __ (2) __ °F,
all available suppression pool cooling is required to be operated.
A. (1) 2 RHR Pumps in one loop
(2) 95
B. (1) 2 RHR Pumps in one loop
(2) 105
C. (1) 1 RHR Pump in each loop
(2) 95
D. (1) 1 RHR Pump in each loop
(2) 105
4
Q4
In accordance with EOI-1, which one of the following rod configurations, after a scram,
confirms that the reactor will remain shut down under all conditions without boron, and
without a Reactor Engineering evaluation?
All Control Rods fully inserted to position 00 except
A. two Control Rods at position 18.
B. ten Control Rods at position 02.
C. one Control Rod at position 02 AND one at 48.
D. one Control Rod at position 48 AND one Control Rod with NO indication (blank).
5
Q5
Which one of the following completes both statements below in accordance with 2-EOI-3,
Secondary Containment Control, Table SC-2, Secondary Containment Area Radiation?
The Table SC-2 area that corresponds to this Area Radiation Monitor (ARM) is
__ (1) __.
The Max Normal radiation value __ (2) __ the same as this ARMs high alarm set point.
A. (1) RHR System I pumps
(2) is
B. (1) RHR System II pumps
(2) is
C. (1) RHR System I pumps
(2) is NOT
D. (1) RHR System II pumps
(2) is NOT
6
Q6
Unit 3 RHR Loop I is in Shutdown Cooling.
What are the electrical power supplies to the associated RHR Pumps?
A. 4KV Shutdown Boards 3EB and 3ED
B. 4KV Shutdown Boards 3EA and 3EC
C. 4KV Shutdown Boards 3EA and 3EB
D. 4KV Shutdown Boards 3EB and 3EC
7
Q7
At 1500, Unit 2 was operating at full power when RECIRC PUMP 2A tripped and the
following occurred:
- OPRM TRIP ENABLED, (2-9-5A window 30) alarms
- OPRM PRE-TRIP CONDITION, (2-9-5A, WINDOW 18) alarms
- OPRM growth algorithm exceeds the pre-trip alarm set point
- LPRM upscale and downscale lights are illuminating and extinguishing
At 1505, the Unit Operator completed inserting the first group of Control Rods on the
Emergency shove sheet and the following conditions exist:
- 2A Recirc Pump Discharge valve is closed
- 2B Recirc pump flow is 47,500 gpm
- Core flow and Reactor power displayed on the attached Power- to -Flow map (red
asterisk)
Which one of the following identifies the required operator action?
[REFERENCE PROVIDED]
A. Raise B Recirc Flow
B. Lower B Recirc Flow
C. Insert a Manual Reactor Scram
D. Insert Control Rods to the 74% Rod Line
8
9
Q8
All three units are operating at 100% power when a Loss of Off-site Power occurs.
- B D/G fails to start
Which one of the following completes the statement below, in accordance with
0-AOI-57-1A, Loss of Offsite Power (161 and 500 KV)/Station Blackout?
The minimum action(s) required to re-energize the affected 480V distribution board(s) is to
transfer 480V Shutdown Board _______ to alternate.
A. 1B ONLY
B. 2A ONLY
C. 1B AND 480V RMOV Board 1B
D. 2A AND 480V RMOV Board 2A
10
Q9
An accident has occurred and the crew has entered 1/ 2-AOI-57-1D, 480V Load Shed.
The following conditions currently exist:
- 250V REACTOR MOV BD 2A UNDERVOLTAGE (2-9-8C Window 4) is in alarm
- The 480V Load Shed signal cannot be reset
Which one of the following completes both statements in accordance with 1/ 2-AOI-57-1D?
The 2A Main Bank Battery charger is required to be returned to service within __ (1) __
after loss of the charger to the battery.
The required operator action to place the battery charger back in service is to __ (2) __.
A. (1) 40 seconds
(2) Place the Charger Power ON switch in EMERGENCY ON
B. (1) 40 seconds
(2) Manually open and re- close the Charger Normal Feeder breaker
C. (1) 30 minutes
(2) Place the Charger Power ON switch in EMERGENCY ON
D. (1) 30 minutes
(2) Manually open and re- close the Charger Normal Feeder breaker
11
Q 10
Unit 2 is operating at 100% power when the following annunciator is received:
- GEN CONDITION MONITOR ABNORMAL, 2-9-8B Window 28
The crew has entered 2-AOI-35-1, Generator Condition Monitor Alarm, and determined
that the alarm is valid.
The crew has reduced Generator load 30MWe and the alarm has not reset.
NOTE; 2-GOI-100-12A, Unit Shutdown from Power Operation to Cold Shutdown and
Reductions in Power During Power Operations
Which one of the following completes the statement below?
2-AOI-35-1 directs Operators to __ (1) __ because __ (2) __.
A. (1) immediately SCRAM and trip the Main Turbine
(2) 2-H2I-35-12A, Hydrogen purity, is less than 90%
B. (1) immediately SCRAM and trip the Main Turbine
(2) the generator is overheating
C. (1) perform a shutdown in accordance with 2-GOI-100-12A
(2) 2-H2I-35-12A, Hydrogen purity, is less than 90%
D. (1) perform a shutdown in accordance with 2-GOI-100-12A
(2) the generator is overheating
12
Q 11
Unit 2 was operating at 100% when an automatic scram occurred due to a high
reactor pressure signal.
Which one of the following completes both statements in accordance with the Immediate
Actions of 2-AOI-100-1, Reactor Scram?
The Unit Operator __ (1) __ required to PAUSE for approximately 5 seconds with the
REACTOR MODE SWITCH in the START & HOT STBY position.
IF REFUEL MODE ONE ROD PERMISSIVE light did not illuminate, the Unit Operator is
allowed to report All rods in__ (2) __ on the full core display.
A. (1) is
(2) ONLY if each rod indicates 00
B. (1) is
(2) if some rods indicate - - and all others indicate 00
C. (1) is NOT
(2) ONLY if each rod indicates 00
D. (1) is NOT
(2) if some rods indicate - - and all others indicate 00
13
Q 12
2-AOI-100-2, Control Room Abandonment, was entered due to toxic gas in the main
control room. All Immediate Operator Actions have been performed.
Which one of the following completes both statements below?
2-AOI-100-2 __ (2) __ direct starting the Main Turbine Lift pumps prior to leaving the
Control Room.
The __ (2) __ valves were controlling Reactor Pressure at the time the operators left the
Main Control Room.
A. (1) does
(2) Main Steam Relief
B. (1) does
(2) Main Turbine Bypass
C. (1) does NOT
(2) Main Steam Relief
D. (1) does NOT
(2) Main Turbine Bypass
14
Q 13
Unit 3 is operating at 100% power.
The Spare RBCCW Pump is disassembled for maintenance.
Subsequently:
- 3A RBCCW Pump trips and CANNOT be restarted
- 3-FCV-070-0048, RBCCW Sectionalizing Valve closes
Which one of the following completes the statements below?
A manual Reactor SCRAM __ (1) __ required in accordance with 3-AOI-70-1, Loss of
Reactor Building Closed Cooling Water.
The temperature of the __ (2) __ is expected to rise for this condition.
A. (1) is NOT
(2) Reactor Building Equipment Drain Sump
B. (1) is NOT
(2) Drywell Equipment Drain Sump
C. (1) is
(2) Reactor Building Equipment Drain Sump
D. (1) is
(2) Drywell Equipment Drain Sump
15
Q 14
All three units are operating at 100% power when the G Air compressor trips.
AIR COMPRESSOR ABNORMAL, (1-9-20B window 29) has alarmed.
Conditions are as follows:
- A and B compressors are running
- C and D compressors failed to start.
- 1-PI-32-20, Control Air header pressure, is lowering
Which one of the following completes both statements in accordance with 0-AOI-32-1,
Loss of Control and Service Air Compressors?
0-FCV-33-1, Service Air crosstie to Control Air valve, automatically opens when control
air header pressure first lowers to __ (1) __ psig.
Reactor SCRAM on Unit 1 is required if Control and Service Air Compressors cannot
maintain Control Air Header pressure above __ (2) __ psig.
A. (1) 70
(2) 55
B. (1) 70
(2) 66
C. (1) 85
(2) 55
D. (1) 85
(2) 66
16
Q 15
Unit 2 is in MODE 4, Cold Shutdown, when a Loss of Shutdown Cooling occurs at 00:00
on April 25.
The crew enters 2-AOI-74-1, Loss of Shutdown Cooling, and is tracking the heatup rate.
- The most limiting Reactor Coolant Temperature is 122° F
- Shutdown Cooling flow CANNOT be established
- It has been 4 days since the plant was shut down
What is the earliest time that Mode 3 will be entered due to rising Reactor Coolant
Temperature?
[REFERENCE PROVIDED]
A. 02:36 on April 25
B. 03:00 on April 25
C. 15:36 on April 25
D. 18:00 on April 25
17
18
Q 16
Unit 1 is in a refueling outage with the fuel pool gates removed and the fuel pool cooling
system in operation in accordance with 1-OI-78, Fuel Pool Cooling and Cleanup
System.
Subsequently, an accident occurred in the spent fuel pool (SFSP) and the crew entered
1-AOI-79-1, Fuel Damage During Refueling.
Which one of the following completes both statements?
In accordance with 1-OI-78 maintaining the SFSP temperature below __ (1) __ °F
minimizes the release of soluble activity.
In accordance with 1-AOI-79-1 if gas bubbles are identified at any time, ___ (2) ___
release should be assumed until RADCON determines otherwise.
A. (1) 100
(2) Iodine
B. (1) 100
(2) Krypton
C. (1) 150
(2) Iodine
D. (1) 150
(2) Krypton
19
Q 17
2-EOI-2, Primary Containment Control, has been entered due to high Drywell Pressure.
Which one of the following completes both statements in accordance with 2-EOI-2?
Operating all available Drywell cooling is required when Drywell Temperature cannot be
maintained below __ (1) __ °F.
In accordance with the Primary Containment Pressure leg of 2-EOI-2 step PC/P-7,
drywell blowers are required to be secured __ (2) __ Suppression Chamber Pressure
exceeds 12 psig.
A. (1) 150
(2) when
B. (1) 150
(2) before
C. (1) 160
(2) when
D. (1) 160
(2) before
20
Q 18
Unit 3 is operating at 100% power.
RX VESSEL PRESSURE HIGH HALF SCRAM (3-9-4 window 9) alarms.
Which one of the following completes the statements below?
The setpoint for this alarm is __ (1) __ psig.
When the initiating condition is corrected and the US directs resetting the half SCRAM in
accordance with 3-OI-99, Reactor Protection System, the OATC will position SCRAM
RESET switch, 3-HS-99-5A/S5, to __ (2) __.
A. (1) 1058
(2) Reset Group 1/4 (left) then Group 2/3 (right)
B. (1) 1058
(2) Reset Group 2/3 (right) then Group 1/4 (left)
C. (1) 1073
(2) Reset Group 1/4 (left) then Group 2/3 (right)
D. (1) 1073
(2) Reset Group 2/3 (right) then Group 1/4 (left)
21
Q 19
A LOCA occurred on Unit 2 and the crew is implementing 2-EOI-2, Primary
Containment Control, Suppression Pool Temperature leg.
Suppression Pool Temperature is 190° F.
Which one of the following completes the statement below?
Action is required if Reactor Pressure is __ (1) __ psig and Suppression Pool Level is __
(2) __ feet.
[REFERENCE PROVIDED]
A. (1) 700
(2) 16
B. (1) 700
(2) 17
C. (1) 900
(2) 15
D. (1) 500
(2) 18
22
23
Q 20
A steam line break inside the drywell occurred and the following conditions currently exist:
- Reactor Pressure is 125 psig
- LI-3-55, Reactor Water Level Flood-up Range, indicates above the Minimum
Indicated Level (MIL) listed in EOI Caution 1.
- Drywell Temperature and Reactor Pressure are in the ACTION REQUIRED region
of Curve 8, RPV Saturation Curve.
Which one of the following completes the statement below, in accordance with EOI
Caution 1?
LI-3-55 __ (1) __ due to __ (2) __.
A. (1) may NOT be used
(2) boiling in the instrument run
B. (1) may be unreliable
(2) boiling in the instrument run
C. (1) may NOT be used
(2) cold calibration conditions
D. (1) may be unreliable
(2) cold calibration conditions
24
Q 21
The crew has determined that the FIRST override listed below (Step ARC/L-4 in 2-EOI-1A,
Which one of the following compete the statements below?
The reason step ARC/L-10 directs the crew STOP and PREVENT all injection into the
RPV Except from is to ___ (1) ___.
RCIC ___ (2) ___ allowed to continue injecting to the RPV.
A. (1) Promote Boron mixing
(2) is
B. (1) Promote Boron mixing
(2) is NOT
C. (1) Reduce core inlet Subcooling
(2) is
D. (1) Reduce core inlet Subcooling
(2) is NOT
25
Q 22
An ATWS has occurred on Unit 3.
The OATC initiated ARI in accordance with the OATC Hard Card.
(No other operator actions have been taken)
Subsequently:
- Reactor Water Level has lowered to (-) 50 inches
- Reactor Pressure peaked at 1130 psig
- 2 MSRVs are currently open
- Reactor Pressure is 900 psig and slowly rising
- Suppression Pool Temperature is 112°F
Which one of the following completes the statements below?
As Reactor Water level lowered the Recirc Pumps __ (1) __ trip automatically.
EOI-1A, ATWS RPV Control directs Operators to __ (2) __ Reactor Water level.
A. (1) did
(2) stop lowering
B. (1) did
(2) continue lowering
C. (1) did NOT
(2) stop lowering
D. (1) did NOT
(2) continue lowering
26
Q 23
Which one of the following completes the statements below?
Stack Release Rate __ (1) __ displayed on the Safety Parameter Display Systems SPDS
OVERVIEW screen.
The ICS/SPDS __ (2) __ to make decisions for the execution of the EOIs.
A. (1) is
(2) can be relied upon as the sole source
B. (1) is
(2) shall only be used in conjunction with the qualified plant instrumentation
C. (1) is NOT
(2) can be relied upon as the sole source
D. (1) is NOT
(2) shall only be used in conjunction with the qualified plant instrumentation
27
Q 24
Fire OPS has responded to a fire in the U3 Aux Instrument Room.
The Incident Commander has requested securing ventilation.
Which one of the following completes both statements below in accordance with
0-AOI-26-1, Fire Response?
If the ventilation cannot be secured from the control switch listed in 0-AOI-26-1
Attachment 1, Ventilation Controls, an Auxiliary Unit Operator (AUO) will be
dispatched to __ (1) __.
Performing this action will support the __ (2) __.
A. (1) trip the breaker for the Air Handling Unit
(2) closure of fire dampers
B. (1) trip the breaker for the Air Handling Unit (2)
automatic initiation of the CO 2 system
C. (1) isolate ventilation by manually closing Aux Instr Rm 3 supply damper 3-31-727
(2) closure of fire dampers
D. (1) isolate ventilation by manually closing Aux Instr Rm 3 supply damper 3-31-727
(2) automatic initiation of the CO 2 system
28
Q 25
Unit 2 is at 50% power.
Subsequently:
- 0-AOI-57-1E, Grid Instability, was entered due to 500KV system instability
Current parameters are:
- System voltage is 505 KV
- System frequency is 59.97 Hz
- U2 Reactive load is +150 MVAR
In accordance with 0-AOI-57-1E, Grid Instability, using the current values, which one of the
following describes the required Unit 2 operator action?
A. Lower Reactor Power
B. Raise Reactor Power
C. Lower Reactive Power
D. Raise Reactive Power
29
Q 26
In accordance with EOI-1, Table L-1, Preferred Injection Systems, what is the highest
Reactor Pressure at which LPCI will inject during the performance of 2-
EOI-Appendix-6B, Injection Subsystems Lineup RHR System I LPCI Mode?
A. 450 psig
B. 320 psig
C. 230 psig
D. 160 psig
30
Q 27
Unit 2 is starting up with Reactor Pressure at 950 psig.
- The 2A CRD Pump trips
- CRD ACCUM PRESS LOW/LEVEL HIGH (2-9-5A, Window 29) is in alarm
- Four CRD SCRAM Accumulator lights are illuminated on the Full Core Display
What sequence of actions is required in accordance with 2-AOI-85-3, CRD System
Failure?
A. Immediately place 1B CRD Pump in service; manual SCRAM is NOT required
B. Immediately attempt one restart of 2A CRD Pump; manual SCRAM is NOT required
C. Manually SCRAM; THEN place the 1B CRD Pump in service
D. Manually SCRAM; THEN attempt one restart of 2A CRD Pump
31
Q 28
Unit 2 is operating at 100% power.
The following alarms are received:
- RX BLDG VENTILATION ABNORMAL (2-9-3D Window 3)
- REACTOR ZONE DIFFERENTIAL PRESSURE LOW (2-9-3D Window 32)
The Reactor Building AUO reports:
- Reactor Building P on PDIC 64-2, El 639' is +0.55 inches of water and lowering
Which one of the following completes the statements below?
An automatic Reactor Zone Static Pressure Isolation __ (1) __ occurred.
EOI-3, Secondary Containment Control, entry__ (2) __ required.
A. (1) has
(2) is
B. (1) has
(2) is NOT
C. (1) has NOT
(2) is
D. (1) has NOT
(2) is NOT
32
Q 29
Unit 3 is in MODE 4, Cold Shutdown.
- RHR Loop I is tagged
- RHR Loop II is in Shutdown Cooling with both pumps in operation
Subsequently, reactor water level lowered to 0 inches due to a leak, and continues to
slowly lower.
The Unit Supervisor directs restoration of Reactor Water Level using Loop II LPCI.
Which one of the following completes the statements below?
RHR Loop II pumps will automatically trip due to a __ (1) __ signal.
In accordance with 3-AOI-74-1, Loss of Shutdown Cooling, prior to injecting with RHR
Loop II LPCI the Unit Operator is required to depress the isolation reset pushbuttons on
Panel __ (2) __.
A. (1) low suction pressure
(2) 3-9-4
B. (1) low suction pressure
(2) 3-9-3
C. (1) suction path interlock
(2) 3-9-4
D. (1) suction path interlock
(2) 3-9-3
33
Q 30
HPCI has an automatic initiation signal.
Which one of the following completes the statement below?
The HPCI PUMP MIN FLOW VALVE, 2-FCV-73-30, will automatically start to close
when flow indicated on 2-FIC-73-33, HPCI System Flow/Control, first exceeds _______
gpm.
A. 620
B. 900
C. 1255
D. 1350
34
Q 31
Unit 1 is operating at 100% power.
The Instrument Mechanics discovered that 1-LIS-3-208B, Reactor Water Level Narrow
Range Level Indicating Switch, will not cause its associated automatic function(s).
The Unit Supervisor declared 1-LIS-3-208B inoperable.
Which one of the following completes both statements?
This condition __ (1) __ prevent an automatic trip of RCIC if actual Reactor Water Level
rises to the high level trip setpoint.
This condition __ (1) __ prevent an automatic trip of HPCI if actual Reactor Water Level
rises to the high level trip setpoint.
A. (1) will
(2) will
B. (1) will
(2) will NOT
C. (1) will NOT
(2) will
D. (1) will NOT
(2) will NOT
35
Q 32
Which one of the following completes both statements below?
When manually aligning Unit 3 Core Spray to inject, the CORE SPRAY SYS I __ (1) __
INJECTION VALVE must be opened first.
When ONLY one pump in a loop is running, 3-OI-75, Core Spray System, requires the
pump flow be throttled to no more than__ (2) __ gpm to avoid pump run-out.
A. (1) INBOARD
(2) 2600
B. (1) INBOARD
(2) 3125
C. (1) OUTBOARD
(2) 2600
D. (1) OUTBOARD
(2) 3125
36
Q 33
The 2A SLC pump is injecting to the Reactor in accordance with 2-EOI-1A, ATWS RPV
Control. The Unit Operator reports SLC Tank Level lowering.
Which one of the following describes the effect of the 2A SLC Pump Discharge Relief
Valve failing open?
Reactor Core Pressure Drop indicated on 2-XR-68-50 will __ (1) __.
Indicated Individual Jet Pump Differential Pressures will __ (2) __.
A. (1) raise
(2) lower
B. (1) raise
(2) not change
C. (1) lower
(2) lower
D. (1) lower
(2) not change
37
Q 34
Unit 2 is operating at 100% when the 2A RPS MG Set trips.
Given the alarm panel below:
Which set of annunciators include ALL the alarms that will illuminate on Panel 2-9-5B for
this event?
Windows 1, 4, 10, 11, 34, along with
A. 18 and 25.
B. 18, 25 and 32.
C. 8, 18, 23 and 25.
D. 8, 18, 23, 25 and 32.
38
Q 35
Unit 3 is operating at 100% power.
Subsequently;
- All 4 SCRAM Solenoid Group A Reset lights are illuminated
- All 4 SCRAM Solenoid Group B Reset lights are extinguished
- All Control Rods inserted to 00
(Assume no Operator actions have been taken)
Which one of the following completes the statement below?
The Control Rods inserted due to operation of the __ (1) __ which __ (2) __ to vent the air
A. (1) ARI valves
(2) energize
B. (1) ARI valves
(2) de-energize
C. (1) Scram pilot solenoid valves
(2) energize
D. (1) Scram pilot solenoid valves
(2) de-energize
39
Q 36
Unit 2 is in MODE 2.
IRM B is on Range 1; ALL other IRMs are on Range 2.
Using the IRMs ICS Screen provided, which one of the following completes the statement
below?
_____ IRM(s) is/are causing a Rod Block.
[REFERENCE PROVIDED]
A. No
B. ONLY B
C. ONLY G
D. B AND G
40
41
Q 37
Unit 2 is in MODE 2.
- All IRMs are on range 4
- During Control Rod withdrawal the following IRM indications are noted:
IRM E - 108/125
IRM F - 118/125
IRM H - 117/125
What is the response of the Reactor Protection System (RPS) and/or Reactor Manual
Control System (RMCS) to these plant conditions?
A. Rod Block ONLY
B. Rod Block and Half Scram RPS A
C. Rod Block and Half Scram RPS B
D. Full Scram
42
Q 38
What are the power supplies to the SRM Channels / detectors?
A. A & B are powered from the A channel + 24VDC System and C & D are powered
from the B channel + 24VDC System.
B. A & C are powered from the A channel + 24VDC System and B & D are powered
from the B channel + 24VDC System.
C. A & B are powered from Division I, 250 VDC System and C & D are powered from
Division II, 250 VDC System.
D. A & C are powered from Division I, 250 VDC System and B & D are powered from
Division II, 250 VDC System.
43
Q 39
A Local Power Range Monitor (LPRM) has been bypassed using BYPASS / HIGH VOLTS
(BYP/HV) ON.
Which one of the following completes the statement below concerning the LPRM?
LPRM detector power output indication __ (1) __ be available at the APRM/LPRM
drawer on Panel 9-14.
The Panel 9-5 Full Core Display __ (2) __ indicate which LPRM is bypassed.
A. (1) will
(2) will
B. (1) will
(2) will NOT
C. (1) will NOT
(2) will
D. (1) will NOT
(2) will NOT
44
Q 40
Which one of the following completes the statements below?
Opening __ (1) __ protects the RCIC pump from overheating.
The normal suction source for RCIC is from the __ (2) __.
A. (1) FCV-71-34, RCIC Pump Minimum Flow Valve
(2) CST
B. (1) FCV-71-34, RCIC Pump Minimum Flow Valve
(2) Suppression Pool
C. (1) FCV-71-25, Lube Oil Cooling Water Supply Valve
(2) CST
D. (1) FCV-71-25, Lube Oil Cooling Water Supply Valve
(2) Suppression Pool
45
Q 41
An ATWS has occurred on Unit 2.
- ADS LOGIC A INHIBIT switch 2-XS-1-159A is in INHIBIT.
- ADS LOGIC B INHIBIT switch 2-XS-1-161A is in INHIBIT.
ADS LOGIC BUS A INHIBITED (2-9-3C Window 18) is in alarm.
ADS LOGIC BUS B INHIBITED (2-9-3C Window 31) did NOT alarm.
Which one of the following completes the statement below?
To ensure that ADS is inhibited, the Unit Operator will dispatch an Auxiliary Unit Operator
to _______ in accordance with 2-ARP-9-3C.
A. open the Auto Blowdown Logic Div II-2 breaker on the 2A 250V RMOV board
B. pull all ADS Solenoid power fuses at 2-25-32, Backup Control Panel
C. pull ADS logic fuses in the Aux Instrument Room on Panel 2-9-30 and 2-9-33
D. place all ADS transfer switches in emergency at 2-25-32, Backup Control Panel
46
Q 42
MSIV Closure-RPS Trip Channel Functional Test, 2-SR-3.3.1.1.8(5), is scheduled to be
performed.
No fuses have been removed due to limit switch failures.
Which one of the following completes the statements below?
To measure MSIV stroke time 2-SR-3.3.1.1.8(5) directs the UO to DEPRESS and HOLD
push-button 2-HS-1-14B, MSIV LINE A INBOARD TEST until __ (1) __.
If the MSIV remains partially closed when the test push button is released, 2-
AOI-1-3, MSIV Closure at Power, requires __ (2) __.
A. (1) the MSIV red and green indicating lights are illuminated
(2) lowering reactor power to 66%
B. (1) the MSIV red and green indicating lights are illuminated
(2) inserting a manual Reactor SCRAM
C. (1) RPS Half-Scram is received
(2) lowering reactor power to 66%
D. (1) RPS Half-Scram is received
(2) inserting a manual Reactor SCRAM
47
Q 43
Which one of the following completes the statements below in the event of a Reactor
Pressure transient?
The first four MSRVs will lift in the Safety Mode at a Reactor Pressure of __ (1) __ psig.
When MSRVs first open, indicated Reactor Water Level will __ (2) __.
A. (1) 1125
(2) rise
B. (1) 1125
(2) lower
C. (1) 1135
(2) rise
D. (1) 1135
(2) lower
48
Q 44
Which one of the following completes both statements below?
Unit 2 SRV Tailpipe Temperature monitoring is available __ (1) __.
In accordance with 2-C-4, RPV Flooding, open SRV tailpipe temperatures __ (2) __ be
used as an indication that the RPV has been flooded to the Main Steam Lines.
A. (1) only on MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1
(2) can
B. (1) only on MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1
(2) can NOT
C. (1) on MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1 and ICS
(2) can
D. (1) on MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1 and ICS
(2) can NOT
49
Q 45
The 3A RFPT is the ONLY RFPT in service and the following conditions currently exist:
- Speed Control RAISE/LOWER switch is pulled up to the FEEDWATER CONTROL
position
- RFPT 3A Individual Speed Control 3-SIC-46-8 Auto / Manual indicator
displays L
- Reactor Water Level Master Controller 3-LIC-46-5 Auto / Manual indicator displays
R
Which one of the following completes both statements?
The output of the __ (1) __ is currently controlling Reactor Water Level.
IF column one is selected on the controller that is controlling Reactor Water Level and the
Ramp Up pushbutton is depressed the controller output __ (2) __ increase.
A. (1) RFPT 3A Individual Speed Controller
(2) will
B. (1) RFPT 3A Individual Speed Controller
(2) will NOT
C. (1) Reactor Water Level Master Controller
(2) will
D. (1) Reactor Water Level Master Controller
(2) will NOT
50
Q 46
Unit 2 is at 100% power.
The Drywell D/P Air Compressor is tagged electrically.
2-OI-64, Primary Containment System, Section 8.6, Maintaining Drywell/Suppression
Chamber D/P Without the Drywell D/P Compressor, is in progress.
- Drywell Pressure 1.48 psig
- Suppression Chamber Pressure 0.33 psig
- Drywell / Suppression Chamber D/P 1.15 psid
Based on these conditions, the Unit Operator is required to vent the _____ in order to
maintain Drywell Pressure and Drywell / Suppression Chamber D/P within their normal
control bands.
A. Drywell to SGT
B. Drywell to the Primary Containment Purge Filter
C. Suppression Chamber to SGT
D. Suppression Chamber to the Primary Containment Purge Filter
51
Q 47
D D/G has been loaded in accordance with 0-SR-3.8.1.1(D) Diesel Generator D Monthly
Operability Test.
Subsequently, 2B Unit Station Service Transformer (USST) Tap Changer fails, causing
DIESEL GEN D OVERLOAD (0-9-23D window 11) to alarm.
Which one of the following predicts the plant response?
A. D D/G load rises and no automatic actions occur
B. D D/G output breaker trips open and the D/G remains operating
C. D D/G output breaker trips open and the D/G automatically shuts down
D. D D/G remains operating and the normal feeder breaker to the D 4KV Shutdown
board trips open
52
Q 48
While transferring Unit 2 Unit Preferred to the Regulating Transformer, the Unit Preferred
voltage begins to oscillate with the Motor-Motor-Generator (MMG) set in parallel with the
Transformer, causing the following annunciator:
- UNIT PFD SUPPLY ABNORMAL (2-9-8B Window 35) alarms due to an
overvoltage condition
NOTE: 0-BKR-280-002/1001, UNIT PFD MMG SET 2 TIE TO BAT BD 2 NORM
FEEDER
0-BKR-280-002/1002, UNIT PFD XFMR 2 TIE TO BATTERY BD 2 ALT FDR
Which one of the following completes the statement below?
Battery board 2 breaker(s) __ (1) __ will trip and the MMG set will __ (2) __.
A. (1) 1001 ONLY
(2) coast to a stop
B. (1) 1001 ONLY
(2) continue to run without excitation
C. (1) 1001 AND 1002
(2) coast to a stop
D. (1) 1001 AND 1002
(2) continue to run without excitation
53
Q 49
The following are indicated on Panel 2-9-8 for Battery Board 2:
BATTERY BD 2 Volts (2-EI-57-37) indicates 245VDC as shown below.
BATTERY BD 2 Amps (2-EI-57-38) indicates (+) 120 amps as shown below.
Which one of the following completes the statements below?
Main Bank Battery #2 is currently __ (1) __.
In accordance with 0-OI-57D, DC Electrical, Battery Board 2 voltage __ (2) __ within 0-
OI-57D limits.
A. (1) discharging
(2) is NOT
B. (1) discharging
(2) is
C. (1) being charged
(2) is NOT
D. (1) being charged
(2) is
54
Q 50
Which one of the following completes both statements concerning the 2B 250V Battery
Charger?
The 2B 250V Battery charger __ (1) __ be aligned to supply Battery Board 5.
There is a/an __ (2) __ interlock that prevents the 2B 250V Battery Charger from
supplying more than one Battery Board at a time.
A. (1) can
(2) mechanical
B. (1) can
(2) electrical
C. (1) can NOT
(2) mechanical
D. (1) can NOT
(2) electrical
55
Q 51
All three units are at 100% power.
EECW is in a normal system lineup.
An Emergency Diesel Generator on Unit 3 auto starts.
Which one of the following completes the statements below?
The __ (1) __ EECW Pumps received an auto start signal.
The EECW Pumps that received an auto start signal provide __ (2) __.
A. (1) A3 and C3
(2) one pump on each EECW header
B. (1) A3 and C3
(2) two pumps on one EECW header
C. (1) B3 and D3
(2) one pump on each EECW header
D. (1) B3 and D3
(2) two pumps on one EECW header
56
Q 52
Which of the following Control Air Compressors are available for service during a Loss of
Off-Site Power?
A. A and B ONLY
B. A and D ONLY
C. B and C ONLY
D. C and D ONLY
57
Q 53
Unit 1 is operating at 100% Reactor Power.
RBCCW Pump 1A trips, resulting in the following:
Which one of the following system loads is being cooled by RBCCW?
A. Drywell Coolers
B. Fuel Pool Cooling Heat Exchangers
C. Reactor Water Cleanup Non-Regenerative Heat Exchangers
D. Reactor Recirculation pump discharge sample cooler
58
Q 54
A Startup is in progress on Unit 2.
- The Rod Worth Minimizer (RWM) is latched into Rod Group 4.
- There are no error messages displayed on the RWM.
- Sequence Control is on.
Operators are withdrawing Control Rods from position 08 to position 12.
Which one of the following will result in a RWM Control Rod Withdraw Block?
A. One Control Rod in Group 4 is inserted to position 06.
B. One Control Rod in Group 5 is selected.
C. The second Control Rod in Group 4 is withdrawn to position 14.
D. The second Control Rod in Group 4 is skipped and the third Rod in Group 4 is
selected.
59
Q 55
Which one of the following is the ATWS/RPT trip setpoint on high Reactor Pressure?
A. 1058 psig
B. 1073 psig
C. 1145 psig
D. 1148 psig
60
Q 56
Which one of the following completes the statement below?
1B Recirc VFD is normally powered by _______.
A. USST 1A
B. USST 1B
C. Start Bus 2A
D. Start Bus 2B
61
Q 57
3-OI-94, Traversing Incore Probe System, section 6.1, Automatic TIP Operation/RPHP
is in progress.
The Auto Start Pushbutton has been depressed and one of the TIP probes is currently in
the core and moving towards the top of the core.
The Reactor scrams on Low Reactor Water Level.
Which one of the following describes the response of the TIP System?
The TIP probe _______.
A. reverses, travels to the indexer, and then the Ball Valve closes
B. continues to the top of the core, reverses, travels to the Indexer, and then the Ball
Valve closes
C. reverses, travels to the in-shield position, and then the Ball Valve closes
D. continues to the top of the core, reverses, travels to the in-shield position, and then the
Ball Valve closes
62
Q 58
Unit 3 is operating at 100% power when the unit scrams due to a steam leak in the
Drywell.
Current conditions are as follows:
- RPV Level is (-) 100 inches
- Reactor Pressure is 550 psig
- Drywell Pressure is 13 psig and rising
- Suppression Chamber Pressure is 12 psig and rising
- Drywell Temperature is 200°F and rising
The crew is implementing 3-EOI Appendix-17B, RHR System Operation Drywell
Sprays.
When the Unit Operator placed keylock switch 3-XS-74-130, RHR SYS II LPCI 2/3
CORE HEIGHT OVRD, in Manual Override, its amber light did NOT illuminate.
The Unit Operator continued in the procedure and manually started 3B RHR pump.
Which ONE of the following completes the statements below?
When 3-HS-74-74A, RHR SYS II DW SPRAY OUTBD VALVE, and 3-
HS-74-75A, RHR SYS II DW SPRAY INBD VALVE, are placed in the OPEN
position, Drywell Temperature will __(1)__.
In accordance with 3-EOI-2, Primary Containment Control, IF Drywell Pressure drops to
__ (2) __ psig Operators are required to STOP Drywell Sprays.
A. (1) Lower
(2) 2.45
B. (1) Lower
(2) 0
C. (1) Continue on the current trend
(2) 2.45
D. (1) Continue on the current trend
(2) 0
63
64
Q 59
RHR Loop II has been placed in service on Unit 1 in accordance with 1-EOI-Appendix
17C, RHR System Operation Suppression Chamber Sprays.
Which one of the following completes the statements below?
While operating solely in the Suppression Chamber Spray Mode, 1-FCV-74-30, RHR SYS
II MIN FLOW Valve, will __ (1) __.
Suppression Pool Cooling __ (2) __ allowed to be placed in service on the same RHR loop
operating in the Suppression Pool Spray Mode.
A. (1) remain open
(2) is
B. (1) remain open
(2) is NOT
C. (1) be closed
(2) is
D. (1) be closed
(2) is NOT
65
Q 60
A LOCA on Unit 2 has resulted in a Reactor SCRAM.
Reactor Water Level has lowered to (-) 140 inches.
The following indications currently exist on Panel 2-9-4:
- MSIV Group A1, 2-IL-64-A1, light extinguished
- MSIV Group A2, 2-IL-64-A2, light illuminated
- MSIV Group B1, 2-IL-64-B1, light extinguished
- MSIV Group B2, 2-IL-64-B2, light illuminated
Which one of the following is the Main Steam System response?
(Assume no Operator actions have been taken)
A. NO MSIVs isolate
B. ONLY Inboard MSIVs isolate
C. ONLY Outboard MSIVs isolate
D. BOTH Inboard and Outboard MSIVs isolate
66
Q 61
Unit 2 is operating at 100% power.
The Unit Operator observes that Generator Hydrogen pressure, 2-PI-35-17A, is lowering.
Which one of the following completes both statements below?
As Generator Hydrogen pressure lowers, Seal oil pressure Turbine End, 2-PI-35-38A
will __ (1) __.
In accordance with 2-OI-35 section 6.1, Adding Hydrogen During Normal Operation, the
Unit Operator __ (2) __ add Hydrogen to the Generator remotely from the Control
Room.
A. (1) lower
(2) can
B. (1) lower
(2) can NOT
C. (1) remain the same
(2) can
D. (1) remain the same
(2) can NOT
67
Q 62
All three Units are in Cold Shutdown and CCW is operating in the OPEN Mode.
A Waste Sample Tank is being aligned for release to the river using 2-FCV-77-61,
Radwaste Discharge Valve Unit 2 Discharge Conduit, in accordance with 0-OI-77A section
8.8, Waste Sample Tank Disposal.
Which one of the following satisfies the MINIMUM requirements for operating a/the
CCW pump(s) to complete this river release?
A. One Unit 2 CCW Pump
B. Two Unit 2 CCW Pumps
C. One Unit 1 and one Unit 2 CCW pump
D. One CCW Pump from each unit
68
Q 63
Unit 2 is at 15% power preparing to synchronize the Main Generator to the Grid when the
following occurs:
- The A SJAE is experiencing reduced First stage performance (stalling).
Which one of the following completes the statements below?
With no operator action, Off-Gas Flow to the Six Hour Hold Up Volume, 2-XR-66-20, will
be __ (1) __.
2-AOI-47-3, Loss of Condenser Vacuum directs the UO to __ (2) __.
A. (1) lowering
(2) Swap to the standby SJAE
B. (1) lowering
(2) Start a Mechanical Vacuum Pump
C. (1) rising
(2) Swap to the standby SJAE
D. (1) rising
(2) Start a Mechanical Vacuum Pump
69
Q 64
Which one of the following completes the statements below?
2-TIS-1-60A, Main Steam Tunnel Temperature, is located on panel __ (1) __.
2-FI-64-38, Reactor Zone Exhaust Flow, is located on panel __ (2) __.
A. (1) 2-9-3
(2) 2-9-25
B. (1) 2-9-3
(2) 2-9-21
C. (1) 2-9-21
(2) 2-9-25
D. (1) 2-9-21
(2) 2-9-21
70
Q 65
In accordance with 0-OI-65, Standby Gas Treatment (SGT) System, upon a Secondary
Containment Isolation, the SGT System is designed to maintain a negative_______ in
Secondary Containment with an in-leakage flow of 12,000 cfm.
A. 0.25 inches of mercury
B. 0.50 inches of mercury
C. 0.25 inches of water
D. 0.50 inches of water
71
Q 66
Which one of the following completes both statements in accordance with OPDP-1,
Conduct of Operations?
When a temporary relief is necessary, the Operator being relieved briefs his/her relief on
abnormal or unusual conditions existing, any evolutions in progress and actions
anticipated during the relief period, and __ (1) __.
Unit Operator temporary reliefs of short duration __ (2) __ required to be logged in NOMS.
A. (1) also provides a Shift Turnover Checklist to his/her relief
(2) are
B. (1) also provides a Shift Turnover Checklist to his/her relief
(2) are NOT
C. (1) where he/she may be reached in the plant during their absence
(2) are
D. (1) where he/she may be reached in the plant during their absence
(2) are NOT
72
Q 67
Unit 3 has experienced a LOCA AND the following conditions exist:
- 3A RHR pump is injecting
- Core Spray Loop II is injecting
- Suppression Pool Level is (-) 5.5 inches
- RPV pressure is 10psig
- Drywell pressure is 6psig
- Suppression Chamber Pressure is 5 psig
- Suppression Pool Temperature is 200º F
- 3-FI-74-50, RHR SYS I Flow, indicates 10,000 gpm
- 3-FI-75-49 CS SYS II Flow indicates 6250 gpm
Which one of the following completes both statements?
RHR __ (1) __ operating within the Net Positive Suction Head (NPSH) limits.
Core Spray __ (2) __ operating within the NPSH limits.
[REFERENCE PROVIDED]
A. (1) is
(2) is
B. (1) is
(2) is NOT
C. (1) is NOT
(2) is
D. (1) is NOT
(2) is NOT
73
74
Q 68
What are the differences between the three Units Standby Gas Treatment (SGT)
controls?
A. Units 1 and 2 each have control switches to operate ALL three SGT trains. Unit 3 has
SGT indications ONLY
B. Unit 1 has control switches to operate two SGT trains ONLY, Unit 2 has control
switches to operate one SGT train ONLY, and Unit 3 has push buttons to start ALL
three SGT trains ONLY
C. Unit 2 has control switches to operate ALL three SGT trains and Units 1 and 3 have
indications ONLY
D. Unit 1 has control switches to operate one SGT train ONLY, Unit 2 has control
switches to operate one SGT train ONLY, and Unit 3 has control switches to operate
one SGT train ONLY
75
Q 69
Which one of the following completes the statement below, in accordance with
OPDP-4, Annunciator Disablement?
Disabled annunciators are identified by a __ (1) __ placed on the disabled annunciator
window.
Each unit __ (2) __ required to carry over the list of disabled annunciators each shift in
the eSOMS Narrative Log.
A. (1) White border
(2) is
B. (1) White border
(2) is NOT
C. (1) Blue border
(2) is
D. (1) Blue border
(2) is NOT
76
Q 70
Which one of the following completes the statements below in accordance with 0-OI-48,
Integrated Computer System?
The Safety Parameter Display System (SPDS) component of the Integrated Computer
System (ICS) displays parameters in __ (1) __ to indicate that the data is bad data.
The SPDS target in the upper right corner of the display will be __ (2) __ if an EOI entry
condition value is reached.
A. (1) cyan
(2) yellow
B. (1) cyan
(2) red
C. (1) blue
(2) yellow
D. (1) blue
(2) red
77
Q 71
Which one of the following completes the statement below in accordance with
2-SR-2, Instrument Checks and Observations?
The Spent Fuel Storage Pool Water Level shall be _______ over the top of irradiated fuel
assemblies seated in the Spent Fuel Storage Pool Racks during movement of irradiated
fuel assemblies in the Spent Fuel Storage Pool.
A. 21.5 feet
B. 22.0 feet
C. 23.5 feet
D. 25.0 feet
78
Q 72
Control Room Ventilation Radiation Monitor 0-RM-90-259A fails upscale and
0-RM-90-259B reads 120 counts per minute.
Which one of the following predicts how the Control Room Ventilation System will
respond?
A. NO ventilation isolation; NEITHER CREV fan auto starts.
B. ONLY Unit 1 and 2 Control Room Ventilation Systems isolate and ONLY the selected
CREV fan auto starts.
C. ALL 3 Units Control Room Ventilation Systems isolate and ONLY the selected CREV
fan auto starts.
D. ALL 3 Units Control Room Ventilation Systems isolate and BOTH CREV fans auto
start.
79
Q 73
Which one of the following completes the statement below?
In accordance with 0-AOI-26-1, Fire Response, in the event of a severe fire,
Operators are required to limit Containment venting to maintain _______ Pump NPSH.
A. RHR
B. CS
C. HPCI
D. RCIC
80
Q 74
Which one of the following completes the statement below in accordance with EPIP-6,
Activation and Operation of the Technical Support Center?
The ______ has command and control in the Technical Support Center (TSC).
A. Outside Unit Supervisor on the unaffected Unit
B. Site Emergency Director
C. Operations Manager
D. Site Emergency Preparedness Manager
81
Q 75
An ALERT has been declared and the TSC has been activated.
Subsequently, RX BLDG AREA RADIATION HIGH, 9-3A, Window 22 alarms due to a
VALID radiological condition.
Which one of the following completes the statements below?
In accordance with the Annunciator Response Procedure (ARP) ___ (1) ___ will use the
Public Address System (PA) to evacuate the area.
The Unit Operator ___ (2) ___ dispatch a Control Bay AUO into the Aux Instrument
Room without TSC concurrence.
A. (1) Control Room personnel
(2) may
B. (1) Control Room personnel
(2) may NOT
C. (1) Technical Support Center personnel
(2) may
D. (1) Technical Support Center personnel
(2) may NOT
82
Q 76
All three units are operating at 100% power.
Operations is scheduled to transfer the A Diesel Auxiliary Board to the alternate supply
breaker in accordance with 0-OI-57B section 8.12, Transfer of 480V Reactor MOV
Boards A, B, and C and Diesel Aux BDs A&B, 3EA, & 3EB.
Which one of the following completes the statements below?
The A Diesel Auxiliary Board is __ (1) __ when being supplied by its alternate power
supply.
If the A Diesel Auxiliary Board subsequently fails to transfer and remains de-energized,
the most limiting Tech Spec required action to restore affected equipment to operable
status requires restoring __ (2) __.
[REFERENCE PROVIDED]
A. (1) operable
(2) the Diesel Auxiliary Board to OPERABLE status within 5 days
B. (1) operable
(2) ALL but one Unit 1 and 2 D/G to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
C. (1) inoperable
(2) the Diesel Auxiliary Board to OPERABLE status within 5 days
D. (1) inoperable
(2) ALL but one Unit 1 and 2 D/G to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
83
Q 77
A Control Air leak develops on Unit 2.
Subsequently;
At 1500 the UO reports that the PSC PUMP SUCTION INBD and OUTBD VALVES are
closed and that RHR SYS I DISCH PRESS, 2-PI-74-51, indicates 45 psig.
At 1520 RHR SYS I DISCH PRESS, 2-PI-74-51 is restored to 55 psig.
NOTE: 2-OI-74, Residual Heat Removal System
2-OI-75, Core Spray System
Which one of the following completes the statements below?
2-AOI-32-2, Loss of Control Air directs aligning condensate storage and supply to restore
discharge piping pressure in accordance with __ (1) __.
At 1520, 2-SR- 3.5.1.1(RHR I), RHR System Venting Loop I, __ (2) __ required.
[REFERENCE PROVIDED]
A. (1) 2-OI-74
(2) is
B. (1) 2-OI-74
(2) is NOT
C. (1) 2-OI-75
(2) is
D. (1) 2-OI-75
(2) is NOT
84
Q 78
An event occurred on Unit 2 which resulted in the following conditions:
- All Rods are inserted
- Reactor Water Level (-)75 inches
- Reactor Pressure 800 psig
- Drywell Pressure 15 psig
- Drywell Temperature 225°F
- Suppression Chamber Pressure 14 psig
- Suppression Pool Level 18 feet
Subsequently;
Reactor pressure rose to 900 psig, which is in the action required area of Curve 4, SRV
Tail Pipe Level Limit.
Which one of the following completes both statements in accordance with 2-EOI-2,
Primary Containment Control?
Implementation of RHR SYSTEM OPERATION DRYWELL SPRAYS, 2-
EOI Appendix 17B __ (1) __ allowed.
Lowering the Reactor Pressure band to exit the required action area of Curve 4, and to
avoid Emergency Depressurization, __ (2) __ allowed.
[REFERENCE PROVIDED]
A. (1) is
(2) is
B. (1) is
(2) is NOT
C. (1) is NOT
(2) is
D. (1) is NOT
(2) is NOT
85
Q 79
Unit 2 is operating at 100% power.
The Unit 2 Unit Operator records the following in 2-SR-2, Instrument Checks and
Observation:
- 0-TI-27-144 Forebay Temperature 93° F
- MIG has verified that 0-TI-27-144 is reading accurately
NOTE: Ultimate Heat Sink (UHS)
In accordance with Unit 2 Tech Specs, what is/are the minimum required action(s)?
[REFERENCE PROVIDED]
A. De-rate Unit 2 to less than 99% Rated Thermal Power ONLY.
B. Declare the UHS INOPERABLE for RHRSW ONLY; de-rate Unit 2 to less than 99%
Power.
C. Declare the UHS INOPERABLE for RHRSW AND EECW; de-rate Unit 2 to less than
99% Power.
D. Declare the UHS INOPERABLE for RHRSW AND EECW, and if temperature
CANNOT be reduced, be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
86
Q 80
A Reactor SCRAM occurred on Unit 2.
HPCI is in service in accordance with EOI Appendix 11C, Alternate RPV Pressure Control
Systems HPCI Test Mode.
Subsequently:
- The Reactor Building AUO reports that there are several inches of water on the
519 elevation floor.
- The BOP Operator reports that 2-LI-64-54A and 2-LI-64-66, SUPPR POOL
WATER LEVEL, indicate (-) 20 inches.
NOTE: 2-EOI Appendix-9 Primary Containment Water Level Monitoring and Equipment
Control
2-EOI APPENDIX-18 Suppression Pool Water Inventory Removal and Makeup
Which one of the following completes the statements below in accordance with EOI-2,
Primary Containment Control?
HPCI __ (1) __ required to be locked out.
__ (2) __ is required to be performed.
A. (1) is
(2) 2-EOI Appendix 9
B. (1) is
(2) 2-EOI Appendix 18
C. (1) is NOT
(2) 2-EOI Appendix 9
D. (1) is NOT
(2) 2-EOI Appendix 18
87
Q 81
A LOCA has occurred on Unit 1 with the following conditions:
- Reactor Water level is (-) 125 inches
- Reactor Pressure is 200 psig
- Drywell Pressure is 20 psig
The US has determined that Reactor Water level CANNOT be restored and maintained
above (-) 162 inches.
In accordance with EOI-1, RPV Control, which one of the following is required?
A. SAMGs
B. Steam Cooling
C. Alternate Level Control
D. Emergency RPV Depressurization
88
Q 82
All three units are operating at 100% power.
At 1445 - 500 KV system voltage is slowly cycling between 515 and 525 KV; the crew
entered 0-AOI-57-1E, Grid Instability.
At 1500 - Off-Site power is lost. All Diesel Generators are supplying their 4KV Shutdown
Boards.
At 1520 - TVAs Transmission Operator (TOp) notifies BFN that Off-Site power will not be
restored for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Which one of the following completes the statements below?
At 1445 the offsite power source __ (1) __ operable.
The earliest time that the NRC must be notified is __ (2) __.
[REFERENCE PROVIDED]
A. (1) was
(2) 1615
B. (1) was
(2) 1900
C. (1) was NOT
(2) 1615
D. (1) was NOT
(2) 1900
89
Q 83
Unit 2 was operating at 100% power when a Reactor SCRAM occurred.
The Unit Operator reports:
- Drywell Pressure 2.20 psig
- Drywell Temperature 162 °F
- Drywell Pressure is slowly rising
NOTE: 2-AOI-64-1, Drywell Pressure and/or Temperature High or Excessive Leakage
into Drywell
2-EOI Appendix-13, Emergency Venting Primary Containment
Which one of the following completes the statement below?
Vent the
A. Drywell in accordance with 2-AOI-64-1.
B. Suppression Chamber in accordance with 2-AOI-64-1.
C. Drywell in accordance with 2-EOI Appendix-13.
D. Suppression Chamber in accordance with 2-EOI Appendix-13.
90
Q 84
Unit 1 is operating at 100% Power when the following alarms are received:
- RX BLDG AREA RADIATION HIGH (1-9-3A, Window 22)
- RX BLDG Elevation 565 East ARM is indicating off-scale high
- RX BLDG Elevation 565 Northeast ARM is indicating 600 mr/hr and stable
The crew entered EOI-3, Secondary Containment Control, and the Shift Manager has
declared an Alert.
Subsequently;
Reports from the field indicate that a primary system is discharging into secondary
containment.
NOTE: 1-EOI-1; RPV Control
0-EOI-4; Radioactivity Release Control
Which one of the following completes both statements?
0-EOI-4, Radioactivity Release Control __ (1) __ required to be entered.
In accordance with Table SC-2, Secondary Containment Area Radiation, the potential
isolation source is the __ (2) __.
A. (1) is
(2) RWCU Isolation valves
B. (1) is NOT
(2) Scram Discharge Volume vents and drains
C. (1) is
(2) Scram Discharge Volume vents and drains
D. (1) is NOT
(2) RWCU Isolation valves
91
Q 85
Unit 2 is operating at 100% power.
REACTOR ZONE EXHAUST RADIATION HIGH (2-9-3A window 21) is in alarm.
The crew entered 2-EOI-3, Secondary Containment Control.
Subsequently the Unit Operator reports:
2-RE-90-142A, Reactor Zone channel A detector A upscale
2-RE-90-142B, Reactor Zone channel A detector B upscale
NOTE; 2-OI-90, Radiation Monitoring System
2-EOI Appendix-8F, Restoring Refuel Zone and Reactor Zone Ventilation Fans
Following Group 6 Isolation
Which one of the follow completes both statements?
An automatic Refuel Zone Ventilation Isolation __ (1) __ occur.
IF the isolation is determined to be invalid and 2-RM-90-142 remains upscale, the
procedure that contains steps to immediately inhibit the 2-RM-90-142 trip signal and
clear the isolation is __ (2) __.
A. (1) will
(2) 2-EOI Appendix-8F
B. (1) will
(2) 2-OI-90
C. (1) will NOT
(2) 2-EOI Appendix-8F
D. (1) will NOT
(2) 2-OI-90
92
Q 86
An ATWS has occurred on Unit 2.
- Reactor Water Level has been intentionally lowered
- HPCI is in service maintaining Reactor Water Level
- Suppression Pool Level is (+) 5 inches and rising
Which one of the following completes the statements below concerning continued HPCI
operation?
2-EOI-5, Curves and Cautions, warns Operators that operating HPCI with a suction
temperature above __ (1) __°F may result in equipment damage.
The procedure that directs performing 2-EOI Appendix-16E, Bypassing HPCI High
Suppression Pool Water Level Suction Transfer Interlock, is __ (2) __.
A. (1) 140
(2) 2-EOI-2, Primary Containment Control, flow chart
B. (1) 140
(2) 2-EOI Appendix 5D, Injection System Lineup HPCI
C. (1) 240
(2) 2-EOI-2, Primary Containment Control, flow chart
D. (1) 240
(2) 2-EOI Appendix 5D, Injection System Lineup HPCI
93
Q 87
At 0300, a LOCA occurred on Unit 2.
At 0345, Venting in accordance with EOI Appendix 13, Emergency Venting Primary
Containment was initiated.
At 0400, DRYWELL/SUPPR CHAMBER RADIATION HIGH (2-9-7 Window 15)
alarmed.
At 0600, the following conditions are reported:
- Reactor water level is stable at (-) 145 inches
- Drywell pressure is 30 psig and rising
- 2-RE-90-272A Drywell Radiation indicates 2500 R/Hr
- Venting is in progress in accordance with 2-EOI-Appendix 13
Assume no further Operator actions.
Which one of the following completes the statements below?
The highest emergency classification required based on the 0600 report is a __ (1) __.
Based on these conditions, injecting SLC __ (2) __ required.
[REFERENCE PROVIDED]
A. (1) Site Area Emergency
(2) is NOT
B. (1) Site Area Emergency
(2) is
C. (1) General Emergency
(2) is NOT
D. (1) General Emergency
(2) is
94
Q 88
Unit 2 startup in accordance with 2-GOI-100-1A, UNIT STARTUP, is in progress.
The following conditions exist:
- IRMs A and F are INOPERABLE
and bypassed
- The Reactor is critical
- The desired period has been
established
- No additional reactivity changes are
made
Subsequently;
When the Unit Operator ranged all IRMs
from range 4 to range 5 the attached IRM
recorder response was noted.
If the IRM with the abnormal trend was declared inoperable, which one of the following
identifies the minimum required action, if any, required by Tech Spec 3.3.1.1, RPS
Instrumentation?
[REFERENCE PROVIDED]
A. No action is required.
B. Condition B
C. Condition A
D. Condition G
95
Q 89
A Reactor SCRAM occurred on U2 and RCIC automatically initiated.
The following conditions currently exist:
- RCIC STEAM LINE FLOW EXCESSIVE (2-9-3B Window 21) is alarming.
room have exceeded the Max Safe value.
Which one of the following completes the statements below?
RCIC __ (1) __ received an auto isolation signal.
2-C-2, Emergency RPV Depressurization, __ (2) __ required.
A. (1) has
(2) is
B. (1) has
(2) is NOT
C. (1) has NOT
(2) is
D. (1) has NOT
(2) is NOT
96
Q 90
Unit 3 is operating at 100% power with no equipment out of service.
3-SR-3.8.1.1(3D), Diesel Generator 3D Monthly Operability Test, is in progress with the
D/G loaded.
Subsequently,
- All Off-Site power is lost.
- Diesel Generators A and C fail to start.
- Diesel Generators 3B and 3C fail to start.
Which one of the following completes the statements below?
When Off-Site Power is lost, the 3D Diesel Generator output breaker will __ (1) __.
The Unit 3 Unit Supervisor __ (2) __ required to perform 0-AOI-57-1A Attachment 12,
Station Blackout Flowchart
A. (1) remain closed
(2) is NOT
B. (1) remain closed
(2) is
C. (1) trip open and then reclose
(2) is NOT
D. (1) trip open and then reclose
(2) is
97
Q 91
Unit 3 is operating at 100% power.
The Unit Operator was inserting Control Rod 34-57 from position 48 to position 00, using
continuous insert when the Unit 3 Unit Preferred MMG set tripped.
The following conditions currently exist:
- Panel 9-9, Cabinet 6 failed to transfer
- The final position of Control Rod 34-57 cannot be determined directly or indirectly
- No rod positions are indicated on the full core display
Which one of the following completes both statements below?
Placing CRD System Flow Controller, 3-FIC-85-11 in manual __ (1) __ enable the Unit
Operator to adjust CRD system flow.
In accordance with 3-AOI-85-4, Loss of RPIS, CRD 34-57 __ (2) __ required to be
declared inoperable.
A. (1) will
(2) is NOT
B. (1) will
(2) is
C. (1) will NOT
(2) is NOT
D. (1) will NOT
(2) is
98
Q 92
Unit 3 is operating at 100% power with Traversing Incore Probe (TIP) operations in
progress to support LPRM calibrations.
The BOP Operator reports that the A TIP detector is stuck in the core.
Maintenance cannot retract the detector within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Which one of the following completes the statements below?
The US is required to enter Tech Spec 3.6.1.3 __ (1) __.
Firing the TIP shear valve __ (2) __ satisfy this Tech Specs Required Action.
[REFERENCE PROVIDED]
A. (1) Condition C
(2) will
B. (1) Condition C
(2) will NOT
C. (1) Condition A
(2) will
D. (1) Condition A
(2) will NOT
99
Q 93
Unit 1 is operating at 100% power.
An electrical fault resulted in de-energizing the Unit 1 +/- 24V Neutron Monitoring Battery
and Battery Charger Channel A.
Which one of the following identifies the minimum required actions, if any?
[REFERENCE PROVIDED]
A. Tech Spec 3.3.1.1, Required Action A.1 OR A.2
B. Tech Spec 3.3.1.1, Required Action A.1 OR A.2 AND C.1.
C. ODCM Table 1.1-2 Actions A, B, C, AND D
D. No Tech Spec OR ODCM Actions are required
100
Q 94
An ALERT has been declared.
Which one of the following items is required on EPIP-3 Appendix A, ALERT Initial
Notification Form.
A. Radiological Conditions
B. Wind speed and direction
C. Lower Emergency Action Levels which also apply
D. Brief description of the Emergency Action Level
101
Q 95
Which choice completes the following statement in accordance with NPG-SPP-10.2,
Clearance Procedure to Safely Control Energy?
For any task where hazardous energy cannot be safely controlled by implementing
NPG-SPP-10.2 requirements, the work is considered working on energized equipment
and must be approved by the __________.
A. Responsible Employee
B. Primary Authorized Employee
C. Plant Manager
D. Work Control Center SRO
102
Q 96
Which one of the following completes the statement in accordance with NPG-SPP-09.4
Attachment 7, 50.59 Evaluation Form?
A proposed plant modification must always have prior NRC approval via a license
amendment if it involves a change to _____.
A. a design basis limit for Primary Containment
B. a Tech Spec system
C. the Technical Requirements Manual (TRM) Bases
D. IST (In-Service Testing) program acceptance criteria
103
Q 97
In accordance with Tech Spec Bases 3.0, LCO Applicability, which one of the following
completes the statement below?
Upon entry into LCO _______, an evaluation shall be made to determine if a Loss
of Safety Function exists.
A. 3.0.4
B. 3.0.5
C. 3.0.6
D. 3.0.7
104
Q 98
All three Units are operating at 100% power.
The 1A & 1B Control Bay Supply Fans tripped and neither can be restarted.
Which one of the following identifies the minimum required Tech Spec actions, if any?
[REFERENCE PROVIDED]
A. No Tech Spec action is required.
B. Tech Spec 3.3.7.1, CREV Instrumentation, Required Action A.1 and D.1.
C. Tech Spec 3.3.7.1, Required Action A.1, D.1, and D.2.
D. Tech Spec 3.7.3, CREV System, Required Action A.1.
105
Q 99
An ATWS has occurred on Unit 2.
2-EOI-1A, ATWS RPV Control, was entered.
The OATC reports that the Reactor is subcritical, but will not remain subcritical under all
conditions without Boron and SLC has failed to inject.
Which one of the following completes both the statements?
NOTE: 2-EOI-1 RPV Control
2-AOI-100-1 Reactor Scram
2-AOI-100-1 __ (1) __ required to be entered at this time.
2-EOI-1 __ (2) __ required to be implemented concurrently with 2-EOI-1A.
A. (1) is
(2) is
B. (1) is
(2) is NOT
C. (1) is NOT
(2) is
D. (1) is NOT
(2) is NOT
106
Q 100
At 1630 the Unit Operator observes valid indications in the Main Control Room which
require an emergency declaration in accordance with EPIP-1, Emergency Classification
Procedure.
At 1637 the Unit Operator reports these indications to the Shift Manager.
Which one of the following indicates the earliest time that the emergency declaration is
required to be made; and the earliest time that the offsite notifications to the state and local
agencies are required to be made?
A. 1645; 1700
B. 1645; 1745
C. 1652; 1707
D. 1652; 1752
107