ML17276B837
| ML17276B837 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/03/2017 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-424/17-301, 50-425/17-301 50-424/OL-17, 50-425/OL-17 | |
| Download: ML17276B837 (28) | |
See also: IR 05000424/2017301
Text
SRO Answer Key
1
A
2
B
3
B
4
A
5
A
6
C
7
D
8
A
9
D
10
B
11
A
12
C
13
C
14
A
15
D
16
B
17
C
18
A
19
C
20
B
21
B
22
A
23
D
24
C
25
C
Name: ________________________
ILT-21 SRO NRC
Student Test
Start Time: _______
Stop Time: _______
ILT-21 SRO NRC
1.
Initial conditions:
- Unit 1 tripped due to a loss of all AC power.
- All RCPs were stopped.
- 1AA02 was re-energized from an off-site source.
- 19102-1, "Loss of All AC Power Recovery with SI Required," was entered.
- 1HV-8103A, B, C, and D, Seal Injection Isolation Valves, were closed.
- CCP 'A' was started with suction aligned to the RWST.
Current condition:
- RWST level is 28% and lowering.
Which one of the following completes the following statements?
Closure of 1HV-8103A, B, C, and D was required to prevent __(1)__.
Per 19102-1, the Shift Supervisor __(2)__ required to go to 19013-1, "Transfer to Cold
Leg Recirculation."
__(1)__
__(2)__
RCP seal damage
is
RCP seal damage
is NOT
an inter-system LOCA
is
an inter-system LOCA
is NOT
A.
B.
C.
D.
Page 1 of 25
ILT-21 SRO NRC
2.
Initial conditions:
- Unit 1 is at 81% reactor power.
- OATC withdraws control rods 1 step and releases the Rod Motion Switch.
- Control rods continue to withdraw.
- The reactor will NOT trip from the Control Room.
- 19211-1, "Response to Nuclear Power Generation / ATWT," is entered.
Current conditions:
- Main turbine will NOT trip using the TRIP pushbuttons.
- RTBs are opened locally by the Control Building Operator.
Which one of the following completes the following statement?
Per 19211-1, the next action the UO is required to perform is to __(1)__,
and
per NMP-EP-110, "Emergency Classification Determination and Initial Action," the Shift
Manager is required to declare a(n) __(2)__ Emergency.
REFERENCES PROVIDED
__(1)__
__(2)__
run back the turbine
Alert
run back the turbine
Site Area
close the MSIVs and BSIVs
Alert
close the MSIVs and BSIVs
Site Area
A.
B.
C.
D.
Page 2 of 25
ILT-21 SRO NRC
3.
Procedure titles as follows:
- 19000-2, "Reactor Trip or Safety Injection"
- 19211-2, "Response to Nuclear Power Generation / ATWT"
Initial conditions:
- Unit 2 is at 100% reactor power.
- Main turbine trips.
- DRPI is de-energized.
- Both Reactor Trip handswitches are taken to TRIP.
Current conditions:
- RTB 'A' red light is NOT lit and green light is NOT lit on the QMCB.
- RTB 'B' red light is lit and green light is NOT lit on the QMCB.
- Both IR NIs indicate approximately 2E -2% and lowering.
- Both IR NIs indicate negative SUR.
Which one of the following completes the following statement?
Based on the given conditions, the Shift Supervisor is required to __(1)__,
and
Bypass Breaker 'A' green light indication __(2)__ be lit on the QMCB.
__(1)__
__(2)__
continue in 19000-2
will
continue in 19000-2
will NOT
transition to 19211-2
will
transition to 19211-2
will NOT
A.
B.
C.
D.
Page 3 of 25
ILT-21 SRO NRC
4.
Given the following:
- Unit 1 is at 100% reactor power.
- ALB34-E02 INVERTERS 1AD1I1 1AD1I11 TROUBLE is received.
- ALB34-E03 120 VAC PANELS 1AY1A 1AY2A TROUBLE is received.
- All Channel I Trip Status lights are lit.
Which one of the following completes the following statements?
Based on the given conditions, the Train 'A' sequencer __(1)__ energized.
Per the Bases of Tech Spec LCO 3.8.9, "Distribution Systems - Operating," when the
affected 120 VAC bus is re-energized at its proper voltage by its associated regulating
transformer, the bus __(2)__ be considered OPERABLE.
__(1)__
__(2)__
is
will
is
will NOT
is NOT
will
is NOT
will NOT
A.
B.
C.
D.
Page 4 of 25
ILT-21 SRO NRC
5.
At time 1000:
- Unit 1 is at 100% reactor power.
- The control room status board indicates that the RCPs are required to be
stopped within 21 minutes if all seal cooling is lost.
At time 1005:
- ACCW supply line to RCP #1 becomes blocked.
- ALB04-A03 ACCW RCP 1 CLR LO FLOW is received.
- ALB04-A04 ACCW RCP 1 CLR OUTLET HI TEMP is received.
- RCP #1 motor bearing and stator winding temperatures are rising.
- 18022-C, "Loss of Auxiliary Component Cooling Water," is entered.
At time 1007:
- The NCP trips.
Which one of the following completes the following statement?
RCP #1 is required to be stopped no later than time __(1)__,
and
after the reactor is tripped, the Shift Supervisor directs the OATC to stop the affected
RCP per __(2)__ direction.
(1) 1015
(2) 18022-C, "Loss of Auxiliary Component Cooling Water"
(1) 1015
(2) 19000-1, "Reactor Trip or Safety Injection"
(1) 1028
(2) 18022-C, "Loss of Auxiliary Component Cooling Water"
(1) 1028
(2) 19000-1, "Reactor Trip or Safety Injection"
A.
B.
C.
D.
Page 5 of 25
ILT-21 SRO NRC
6.
At time 1200:
- Unit 1 is experiencing a turbine runback.
- Control bank 'D' rods are at 140 steps.
- Highest NI power is 92%.
- Highest RCS Delta T is 90%.
At time 1205:
- Control bank 'D' rods are at 116 steps.
- Highest NI power is 76%.
- Highest RCS Delta T is 83%.
At time 1210:
- Main turbine load is stable.
- RCS Tavg is 2 °F below Tref.
- The OATC has requested a 2-step rod withdrawal for temperature control.
Which one of the following completes the following statement?
Based on the given conditions, ALB10-D04 ROD BANK LO-LO LIMIT is first expected
to alarm at time __(1)__,
and
at time 1210 and per NMP-OS-001, "Reactivity Management Program," guidance, the
Shift Supervisor is __(2)__ to authorize a 2-step control rod withdrawal for Tavg
control.
REFERENCES PROVIDED
__(1)__
__(2)__
1200
allowed
1200
NOT allowed
1205
allowed
1205
NOT allowed
A.
B.
C.
D.
Page 6 of 25
ILT-21 SRO NRC
7.
Given the following:
- Unit 2 experienced a turbine runback.
- ALB10-C04 ROD BANK LO LIMIT is received.
- ALB10-D04 ROD BANK LO-LO LIMIT is received.
- The following RWST parameters are indicated:
- Temperature is 43 °F.
- Level is 95%.
Which one of the following completes the following statement?
Tech Spec LCO 3.5.4, "Refueling Water Storage Tank (RWST)," is NOT met due to
RWST __(1)__,
and
per the Bases of Tech Spec LCO 3.5.4, this parameter limit ensures __(2)__.
(1) Level
(2) sufficient borated water is available to support the ECCS during the injection
phase of a design basis main steam line break
(1) Level
(2) sufficient borated water is available to support the ECCS during the injection
phase of a design basis loss of coolant accident
(1) Temperature
(2) peak clad temperature is controlled by limiting the containment pressure
reduction effect of Containment Spray during a main steam line break
(1) Temperature
(2) peak clad temperature is controlled by limiting the containment pressure
reduction effect of Containment Spray during a loss of coolant accident
A.
B.
C.
D.
Page 7 of 25
ILT-21 SRO NRC
8.
Initial conditions:
- Unit 2 reactor trip and SI occurred due to a LOCA.
- Containment pressure is 29 psig.
- Containment Cooling Units #1 and #2 are tagged out.
- Containment Spray (CS) pumps are being aligned for recirculation using
19013-2, "Transfer to Cold Leg Recirculation."
- An ALERT Emergency has been declared due to Loss of the RCS Barrier.
Current conditions:
- 2BA03 de-energizes due to a fault.
- 2HV-9002A, CS Pump 'A' Containment Sump Suction IRC, will NOT open.
Which one of the following completes the following statement?
Per 10020-C, "EOP and AOP Rules of Usage," initiation of 18031-2, "Loss of Class 1E
Electrical Systems," __(1)__ allowed to address the loss of 2BA03,
and
based on the given conditions, an EAL classification upgrade __(2)__ required.
REFERENCES PROVIDED
__(1)__
__(2)__
is
is
is
is NOT
is NOT
is
is NOT
is NOT
A.
B.
C.
D.
Page 8 of 25
ILT-21 SRO NRC
9.
At time 1055:
- Unit 2 is in Mode 5.
- Containment integrity is NOT established.
- Pressurizer level is 27%.
- All pressurizer safety valves are removed.
At time 1100:
- A loss of off-site power occurs.
- DG2A starts and trips on overspeed.
- CCW Train 'B' pumps will NOT start following the load sequence.
- RCS temperature is 200 °F and rising.
Which one of the following completes the following statement?
At time 1115, the Shift Manager declares a(n) __(1)__ per NMP-EP-110, "Emergency
Classification Determination and Initial Action,"
and
per NMP-EP-111, "Emergency Notifications," State and Local Agencies are required to
be notified of the initial declaration no later than time __(2)__.
REFERENCES PROVIDED
__(1)__
__(2)__
1125
1130
ALERT
1125
ALERT
1130
A.
B.
C.
D.
Page 9 of 25
ILT-21 SRO NRC
10.
Initial conditions:
- Unit 1 is at 100% reactor power.
- A total loss of feedwater occurs.
- The reactor will NOT trip.
- 19211-1, "Response to Nuclear Power Generation / ATWT," is in progress.
Current conditions:
- Shift Supervisor is performing the step to "Check Core Exit TCs - LESS THAN
1200 °F."
- CETCs are 1208 °F and lowering.
Which one of the following completes the following statement?
The EOP basis for tripping the main turbine during this event is to __(1)__,
and
the Shift Supervisor is required to __(2)__.
(1) maintain SG inventory
(2) go to SACRG-1, "Severe Accident Control Room Guideline Initial Response"
(1) maintain SG inventory
(2) remain in 19211-1, "Response to Nuclear Power Generation / ATWT"
(1) allow the RCS heatup to add negative reactivity
(2) go to SACRG-1, "Severe Accident Control Room Guideline Initial Response"
(1) allow the RCS heatup to add negative reactivity
(2) remain in 19211-1, "Response to Nuclear Power Generation / ATWT"
A.
B.
C.
D.
Page 10 of 25
ILT-21 SRO NRC
11.
Procedure 13719-1, "Spent Fuel Pool Cooling and Purification," sections as follows:
- Section 4.2.2, "SFP Makeup from the RWST through the SFP Purification Loop"
- Section 4.2.4, "SFP Makeup from the RMWST"
Initial conditions:
- Unit 1 is defueled.
- Transfer canal is drained for transfer cart inspection.
- Spent fuel shuffle is in progress in the SFP.
Current conditions:
- ALB05-E02 SPENT FUEL PIT LO LEVEL is received.
- Personnel in the FHB report SFP level is slowly lowering.
- 18030-C, "Loss of Spent Fuel Pool Level or Cooling," is entered.
Which one of the following completes the following statement?
To mitigate the consequences of the event, the Shift Supervisor is required to direct
makeup to the SFP using 13719-1, Section __(1)__,
and
per the Bases of Tech Spec LCO 3.7.15, "Fuel Storage Pool Water Level," maintaining
the required minimum water level in the SFP __(2)__ ensure adequate iodine
decontamination factors are met for a fuel handling accident.
__(1)__
__(2)__
4.2.2
will
4.2.2
will NOT
4.2.4
will
4.2.4
will NOT
A.
B.
C.
D.
Page 11 of 25
ILT-21 SRO NRC
12.
Initial conditions:
- Unit 1 reactor startup is in progress per 12003-C, "Reactor Startup (Mode 3 to
Mode 2)."
- Intermediate Range NIs each indicate 4E -5%.
- SR BLOCK PERMISSIVE P-6 on the BPLB is lit.
Current conditions:
- Intermediate Range N35 indication is pegged low.
- SR BLOCK PERMISSIVE P-6 on the BPLB is NOT lit.
Which one of the following completes the following statement?
Based on the given conditions and per the Bases of Tech Spec LCO 3.3.1, "Reactor
Trip System (RTS) Instrumentation," the P-6 Interlock function __(1)__ OPERABLE,
and
per 18002-C, "Nuclear Instrumentation System Malfunction," placing the affected
channel's Level Trip switch in BYPASS aligns NI __(2)__ power to the SSPS input
relays.
__(1)__
__(2)__
is
control
is
instrument
is NOT
control
is NOT
instrument
A.
B.
C.
D.
Page 12 of 25
ILT-21 SRO NRC
13.
Given the following:
- Unit 2 is in Mode 6 with core reload in progress.
- RHR pump 'B' is in service.
- RHR pump 'A' is tagged out.
- Shift Supervisor has authorized RHR pump 'B' to be stopped to position a fuel
assembly.
Which one of the following completes the following statement?
Per the Bases of Tech Spec LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant
Circulation - High Water Level," stopping of the RHR pump is allowed to perform core
alterations within the vicinity of the RCS __(1)__ leg nozzles,
and
per Tech Spec LCO 3.9.5, the crew is authorized to stop the running RHR pump for a
maximum of __(2)__ hour(s) in an eight hour period.
__(1)__
__(2)__
cold
1
cold
2
hot
1
hot
2
A.
B.
C.
D.
Page 13 of 25
ILT-21 SRO NRC
14.
Initial conditions:
- Unit 2 is at 45% reactor power.
- SG #3 MFRV fails open and can NOT be closed.
Current conditions:
- An automatic reactor trip occurs.
- Reactor Trip Breaker 'A' is open.
- Reactor Trip Breaker 'B' is NOT open.
Which one of the following completes the following statements?
With no operator action, the Main Feed Isolation Valves (MFIVs) __(1)__ closed.
Based on the given conditions, per NMP-AD-031, "SNC Reportability Roles,
Responsibilities, and Fleet Requirements," the NRC Operations Center is required to
be notified in no later than __(2)__ hours.
REFERENCES PROVIDED
__(1)__
__(2)__
are
4
are
8
are NOT
4
are NOT
8
A.
B.
C.
D.
Page 14 of 25
ILT-21 SRO NRC
15.
Initial conditions:
- Unit 1 just tied the main generator to the grid following a 17 day refueling outage.
- ALB05-E02 SPENT FUEL PIT LO LEVEL is received.
- 18030-C, "Loss of Spent Fuel Pool Level or Cooling," is in progress.
Current conditions:
- SFP temperature is 110 °F.
- The crew is determining the time to reach 200 °F in the SFP.
Which one of the following completes the following statement?
With no operator action, the SFP will first reach 200 °F in __(1)__ hours,
and
per the Bases of Tech Spec LCO 3.7.15, "Fuel Storage Pool Water Level," the
minimum required water level ensures the radiological consequences of a fuel handling
accident are within the acceptable limits of __(2)__.
REFERENCES PROVIDED
__(1)__
__(2)__
11
11
16
16
A.
B.
C.
D.
Page 15 of 25
ILT-21 SRO NRC
16.
Initial conditions:
- Unit 2 is at 100% reactor power.
- CCP 'B' is tagged out.
Current condition:
- 2AA02-05, Normal Incoming Breaker, trips open.
Which one of the following completes the following statement?
Following the 2AA02-05 Normal Incoming breaker trip, the sequencer will open the
affected __(1)__ side 4160 VAC to 480 VAC breakers,
and
per Tech Spec LCO 3.8.1, "AC Sources - Operating," the Shift Supervisor is required to
declare CCP 'A' inoperable by no later than __(2)__ hours.
__(1)__
__(2)__
low (480 VAC)
4
low (480 VAC)
24
high (4160 VAC)
4
high (4160 VAC)
24
A.
B.
C.
D.
Page 16 of 25
ILT-21 SRO NRC
17.
Initial conditions:
- Unit 2 is at 100% reactor power.
- TPCCW cooling to the air compressors is reduced due to a small pipe break.
- Crew is implementing 18023-C, "Loss of Turbine Plant Cooling and Closed
Cooling Water Systems," Section B, for loss of TPCCW.
Current condition:
- Instrument air pressure is degrading.
Which one of the following completes the following statement?
Per 13710-2, "Service Air System," the crew is required to align __(1)__ water to the air
compressors,
and
if air compressor cooling is NOT adequate, the Shift Supervisor is required to initiate
__(2)__ per 18023-C.
__(1)__
__(2)__
demineralized
18028-C, "Loss of Instrument Air"
demineralized
18013-C, "Rapid Power Reduction"
utility
18028-C, "Loss of Instrument Air"
utility
18013-C, "Rapid Power Reduction"
A.
B.
C.
D.
Page 17 of 25
ILT-21 SRO NRC
18.
Initial conditions:
- Unit 2 reactor trip and SI occurs due to a large break LOCA.
- All RCPs are stopped.
- 2AA02 de-energizes due to a fault.
Current conditions:
- 19221-2, "Response to Inadequate Core Cooling," is in progress.
- ACCW pump #2 trips.
- Containment pressure is 12 psig.
- CETCs are 1220 °F and rising.
- SG NR levels are as follows:
SG #1 is 30%
SG #2 is 21%
SG #3 is 34%
SG #4 is 26%
Which one of the following completes the following statement?
Per 19221-2, the Shift Supervisor __(1)__ required to direct the start of at least one
RCP,
and
will transition to 19010-2, "Loss of Reactor or Secondary Coolant," when at least two
RCS WR Hot Leg temperatures first lower to less than __(2)__ °F.
__(1)__
__(2)__
is
375
is
700
is NOT
375
is NOT
700
A.
B.
C.
D.
Page 18 of 25
ILT-21 SRO NRC
19.
Given the following:
- Unit 1 is at 100% reactor power.
Which one of the following completes the following statement?
Per Tech Spec LCO 3.4.16, "RCS Specific Activity," the specific activity of the reactor
coolant shall be < __(1)__ Ci/gm Dose Equivalent I-131,
and
operating within this limit ensures that the off-site dose will be limited to within a small
fraction of the dose guideline values in the event of a __(2)__.
__(1)__
__(2)__
0.1
0.1
loss of all AC power
1.0
1.0
loss of all AC power
A.
B.
C.
D.
Page 19 of 25
ILT-21 SRO NRC
20.
Initial conditions:
- Unit 1 is at 100% reactor power.
- A steam leak exists in containment.
Current conditions:
- ALB01-E06 CNMT HI TEMP is received.
- IPC data for containment temperature is collected.
Which one of the following completes the following statement?
Based on the IPC data provided, the Tech Spec LCO 3.6.5, "Containment Air
Temperature," surveillance for containment temperature (Tech Spec SR 3.6.5.1)
__(1)__ within Tech Spec limits,
and
per the Bases of Tech Spec LCO 3.4.15, "RCS Leakage Detection Instrumentation,"
containment normal and reactor cavity sumps remain OPERABLE as long as the
steam leak in containment does not interfere with the system's ability to detect a 1 gpm
unidentified leak from the RCS in approximately __(2)__ hour(s).
REFERENCES PROVIDED
__(1)__
__(2)__
is
12
is
1
is NOT
12
is NOT
1
A.
B.
C.
D.
Page 20 of 25
ILT-21 SRO NRC
21.
Initial conditions:
- Unit 2 is at 100% reactor power.
- SIP 'A' is tagged out.
Current conditions:
- CCP 'B' is declared inoperable.
- As a result, a second entry into Tech Spec LCO 3.5.2, "ECCS - Operating," is
made 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> after the initial entry.
Which one of the following completes the following statement?
Per Tech Spec Rules of Use and Application, the maximum Completion Time allowed
for completing the Required Actions of Tech Spec LCO 3.5.2 is __(1)__ hours,
and
in order to apply the Completion Time extension, the component that must first be
returned to OPERABLE is __(2)__.
REFERENCES PROVIDED
__(1)__
__(2)__
88
CCP 'B'
88
SIP 'A'
96
CCP 'B'
96
SIP 'A'
A.
B.
C.
D.
Page 21 of 25
ILT-21 SRO NRC
22.
Initial conditions:
- Unit 2 is in Mode 3.
- RCP #2 is in operation.
- RCP #2 is experiencing high vibrations.
Current conditions:
- RCP #1 is available for starting.
- SG #1 NR level is 11%.
Which one of the following completes the following statements?
Per Tech Spec LCO 3.4.5, "RCS Loops - Mode 3," all RCPs may be stopped for less
than or equal to one hour per eight hour period provided that core outlet temperature is
maintained at least __(1)__ °F below saturation temperature.
Based on the given conditions and per the Bases of Tech Spec LCO 3.4.5, RCS
loop #1 __(2)__ an OPERABLE RCS loop.
__(1)__
__(2)__
10
is
10
is NOT
50
is
50
is NOT
A.
B.
C.
D.
Page 22 of 25
ILT-21 SRO NRC
23.
Initial conditions:
- Unit 1 is at 100% reactor power.
- A containment fire alarm is received.
Current conditions:
- A containment entry is required to confirm the fire alarm.
- Moveable In-core Detectors (MIDS) are fully inserted in their storage locations.
Which one of the following completes the following statement?
Per 00303-C, "Containment Entry," the Shift Supervisor is required to verify that the
MIDS panel power supply breakers are off and __(1)__,
and
the RP Manager __(2)__ required to authorize this entry.
__(1)__
__(2)__
danger tagged
is
danger tagged
is NOT
locked with RP locks
is
locked with RP locks
is NOT
A.
B.
C.
D.
Page 23 of 25
ILT-21 SRO NRC
24.
Initial conditions:
- Unit 1 is at 12% reactor power ramping up to full power following an outage.
- ALB05-C01 HIGH RADIATION ALARM is received.
- SG #2 has a confirmed 40 gpd tube leak.
- 18009-C, "Steam Generator Tube Leak," is entered.
Current conditions:
- 18009-C, Attachment 1, "Operation with a Minor Tube Leak," is in progress.
- SG #2 leak rate is rising.
Which one of the following completes the following statements?
1RE-724, Steam Line Radiation, __(1)__ available to monitor SG leak rate.
Based on the given conditions and per 18009-C, if all radiation monitor indications are
lost, the Shift Supervisor __(2)__ required to commence a Unit shutdown.
__(1)__
__(2)__
is
is
is
is NOT
is NOT
is
is NOT
is NOT
A.
B.
C.
D.
Page 24 of 25
ILT-21 SRO NRC
25.
Initial conditions:
- Unit 1 reactor trip and SI occurred due to a LOCA.
- 19010-1, "Loss of Reactor or Secondary Coolant," is in progress.
- Containment Spray pumps are NOT running.
- ALB06-F04 RWST LO-LO LEVEL is received.
Current conditions:
- Containment pressure is 32 psig.
- The STA recommends a transition to 19251-1, "Response to High Containment
Pressure."
Which one of the following completes the following statement?
Based on the given conditions, the recommendation to transfer to 19251-1 is based on
a Containment __(1)__ path,
and
the Shift Supervisor __(2)__ required to transition to 19013-1, "Transfer to Cold Leg
Recirculation," before completing 19251-1.
__(1)__
__(2)__
RED
is
RED
is NOT
ORANGE
is
ORANGE
is NOT
A.
B.
C.
D.
Page 25 of 25
ILT-21 SRO Exam Provided References Index
1.
ICs, Threshold Values, and Basis, Pages 125,
126, and 127 (Figures 1, 2, and 3) (rev. 9.0)
2.
Unit 1 Core Operating Limits Report fCOLR), Figure 3, Rod Bank Insertion Limits
Versus % of Rated Thermal Power, (cycle 19)
3.
NMP-AD-031, SNC Reportability Roles, Responsibilities, and Fleet Requirements,
Pages 41 47 and 113 184 (rev. 8.0)
4.
Unit 1 Plant Technical Data Book (P1DB), Tab 26, Spent Fuel Pool
Time to 200
°F, (rev. 1 .0)
5.
Unit 1 Integrated Plant Computer Screenshot, Containment Parameters
6.
Unit 1 Tech Spec 3.5.2, ECCS
Operating, Page 3.5.2-1 (rev. 176)