ML17354B270
| ML17354B270 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/20/2017 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-261/17-301 | |
| Download: ML17354B270 (27) | |
See also: IR 05000261/2017301
Text
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
76
(1 point)
Given the following:
The plant is operating at 100% RTP
A planned maintenance item is scheduled for the shift has a YELLOW risk status
Subsequently:
PCV-455C, PZR PORV fully opens
Attempts to close the valve have failed
RC-536, PORV BLOCK Valve is manually CLOSED
The plant remains on line
Which ONE of the following correctly completes the statements below?
Based on these conditions, Pressurizer PORV Block Valve RC-536 is
(1)
The updated Risk Profile for the planned maintenance reveals that the risk is an
Elevated YELLOW status.
lAW OMM-048, WORK COORDINATION AND RISK ASSESSMENT, the planned
maintenance item
(2)
be released for work this shift without authorization
from the Plant Manager, due to the change in risk status.
A.
(1) OPERABLE
(2) can
B.
(1) inoperable
(2) can
C.
(1) OPERABLE
(2) can NOT
D.
(1) inoperable
(2) can NOT
Page 76 of 100
Robinson Nuclear Plant
IL-1 7 RNP SRO NRC Examination
Question:
77
(1 point)
Given the following:
The plant tripped from 100% power
RCS Bleed and Feed has been established per FRP-H.1, RESPONSE TO LOSS
OF SECONDARY HEAT SINK
Current Conditions:
AFW flow has been restored
All Narrow Range S/G levels remain OFF-SCALE LOW
Which ONE of the following correctly completes the statements below?
Operators
(jj
required to establish a set Narrow Range level in at least one
S/G before terminating RCS Bleed and Feed.
Operators will terminate RCS Bleed and Feed in
A.
(1)are
(2) FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK
B.
(1)are
(2) EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT
C.
(1)areNOT
(2) FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK
D.
(1)areNOT
(2) EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT
Page 77 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
78
(1 point)
Given the following:
A Station Blackout has occurred from 100% power
The crew is performing actions of ECA-0.0, LOSS OF ALL AC POWER
Immediate actions are complete
Offsite power is available to re-energize the Start-up Transformer (SUT)
APP-009-B5, MAIN TRANSF FAULT TRIP, alarm is ILLUMINATED.
Subsequently:
E-1 is restored with EDG A
Transmission Maintenance has taken action such that APP-009-B5 is now
extinguished.
Which ONE of the following correctly completes the statements below?
lAW EOP-ECA-0.0, the CRS is required to use procedure
(1)
to restore
power via the SUT.
Prior to restoring power via the SUT, the appropriate procedure
(2)
require
the crew to ensure the Main Generator Lockout Relays 86P and 86BU are reset.
OP-603, ELECTRICAL DISTRIBUTION
OP-603-3, RESETTING HIGH IMPEDANCE FAULTS
86P, GENERATOR LOCKOUT RELAY, PRIMARY
86BU, GENERATOR LOCKOUT RELAY, BACKUP
A.
(1) OP-603
(2) does NOT
B.
(1)OP-603
(2) does
C.
(1) OP-603-3
(2) does NOT
D.
(1) OP-603-3
(2) does
Page 78 of 100
Robinson Nuclear Plant
ILC-1 7 RNP SRO NRC Examination
Question:
79
(1 point)
Given the following:
The plant is in MODE 3 following a reactor trip
No Battery Chargers are operating
APP-036-D3, BATT NB LO VOLT, has alarmed
Battery A voltage is 122.8 Volts and slowly lowering
Battery B voltage is 125.0 Volts and slowly lowering
Subsequently, it is determined that Battery voltages are lowering at the following rates:
Battery A
- 0.8 volts/minute
Battery B
- 0.5 volts/minute
Which ONE of the following correctly completes the statements below?
Assuming the Battery voltages lower at a constant rate, the approximate time frame that
voltages will lower to the required EAL thresholds is
(1)
minutes.
At 1000, battery voltages lowered to the required EAL thresholds
At 1002, maintenance reports that restoration of one Battery Charger will take at LEAST 30
minutes
At 1005, the Shift Manager declared a Site Area Emergency SS2.1
The declaration at 1005
(2)
contrary to the Robinson Nuclear Plant Emergency Plan.
REFERENCE PROVIDED
A.
(1) 30-32 minutes
(2) was
B.
(1) 30-32 minutes
(2) was NOT
C.
(1) 36-38 minutes
(2) was NOT
D.
(1) 36-38 minutes
(2) was
Page 79 of 100
Robinson Nuclear Plant
ILC-1 7 RNP SRO NRC Examination
Question:
80
(1 point)
Given the following:
The plant is operating at 100% power
Emergency Diesel Generator (EDG) B is running paralleled to Bus E-2
The Control Room has just received a notification of an imminent cyber-attack on
the grid from the NRC
AOP-026, GRID INSTABILITY, has been implemented
Which ONE of the following correctly completes the statements below?
lAW AOP-026, operators are required to
(1)
EPP-25, ENERGIZING SUPPLEMENTAL PLANT EQUIPMENT USING THE DSDG,
(2)
required to be implemented for these conditions.
A.
(1) shutdown EDG B
(2) is
B.
(1) shutdown EDG B,,
(2) is NOT
C.
(1) ensure EDG B is operating as the sole source of power to Bus E-2
(2) is
D.
(1) ensure EDG B is operating as the sole source of power to Bus E-2
(2) is NOT
Page $0 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
81
(1 point)
Given the following:
The crew is implementing FRP-Hi, RESPONSE TO LOSS OF SECONDARY
HEAT SINK
The CST is intact, level is 15% and lowering
Which ONE of the following correctly completes the statements below?
The order in which the CRS is required to attempt to restore Feed Flow to S/Gs lAW
FRP-H.1 is AFW,
(1)
Subsequently, APP-006-E6, CST LO/LO-LO LEVEL alarms
The specific steps to reposition valves to align Service Water as a backup to the AFW
system are located in
(2)
OP-402, AUXILIARY FEEDWATER SYSTEM
FRP-H.1, ATTACHMENT 1, ALIGNING ALTERNATE WATER SUPPLY TO AFW
PUMPS
A.
(1) Main Feedwater, Condensate
(2) OP-402
B.
(1) Main Feedwater, Condensate
(2) ATTACHMENT I of FRP-H.1
C.
(1) Condensate, Main Feedwater
(2) OP-402
D.
(1) Condensate, Main Feedwater
(2) ATTACHMENT 1 of FRP-H.I
Page 81 of 100
Robinson Nuclear Plant
ILC-1 7 RNP SRO NRC Examination
Question:
82
(1 point)
Given the following:
The plant is stabilized at 3% power with GP-003, NORMAL PLANT STARTUP FROM HOT
SHUTDOWN TO CRITICAL, in progress
The BOP is performing OWP-O1 1, NUCLEAR INSTRUMENTATION (NI), for Intermediate
Range Channel N-35 to support l&C Troubleshooting activities
When the LEVEL TRIP switch for N-35 is positioned to BYPASS, the BOP observes the
indications of a blown fuse on the N-35 drawer
The reactor remains at 3% power
The CRS has entered Condition F of LCO 33.1, REACTOR PROTECTION SYSTEM
(RPS) INSTRUMENTATION
Which ONE of the following correctly completes the statements below?
The
(1)
fuse is blown.
lAW Technical Specification, the CRS
(2)
allowed to enter MODE 1.
REFERENCE PROVIDED
A.
(1) Control Power
(2) is
B.
(1) Control Power
(2) is NOT
C.
(1) Instrument Power
(2) is NOT
D.
(1) Instrument Power
(2) is
Page 82 of 100
Robinson Nuclear Plant
ILC-1 7 RNP SRO NRC Examination
Question:
83
(1 point)
Given the following:
A WGDT is IN SERVICE
Chemistry informs the CRS that as a result of a fuel element failure, A WGDT
activity is 2.6 X
Curies Noble Gas
Subsequently, vent header pressure is 2.3 PSIG
Which ONE of the following correctly completes the statements below?
The CRS will direct vent header pressure to be reduced
(ii
the A WGDT is
removed from service.
ODCM 3.2.1 states that the dose rate due to radioactive materials in gaseous effluents
released from the site boundary shall be limited to the following: For radionoble gases,
(2)
to total body.
A.
(1)AFTER
(2) < 300 mrem/yr
B.
(1) BEFORE
(2) < 300 mrem/yr
C.
(1)AFTER
(2) < 500 mrem/yr
D.
(1) BEFORE
(2) <500 mrem/yr
Page 83 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
84
(1 point)
Given the following:
Core Alterations are on-going in accordance with GP-O1O, REFUELING
R-2, CV Low Range, alarms (HIGH LED is LIT)
Which ONE of the following correctly completes the statements below?
To determine the correct R-2 setpoint the operator is required to use
(1)
R-2 was subsequently determined to be inoperable
An HP Technician is providing continuous coverage with a Portable Area Radiation
Monitor
(2)
continue.
A.
(1) the Setpoint Change and Log Record of OMM-014, RADIATION MONITOR
SETPOINTS
(2) can
B.
(1) the Setpoint Change and Log Record of OMM-014, RADIATION MONITOR
SETPOINTS
(2) can NOT
C.
(1) Section 3.1, Monitor Alarm Setpoint Determination, of the OFFSITE DOSE
CALCULATION MANUAL (ODCM)
(2) can
D.
(1) Section 3.1, Monitor Alarm Setpoint Determination, of the OFFSITE DOSE
CALCULATION MANUAL (ODCM)
(2) can NOT
Page $4 of 100
Robinson Nuclear Plant
ILC-1 7 RNP $RO NRC Examination
Question:
85
(1 point)
Given the following:
The crew is in EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT
Containment pressure is 5 psig and slowly rising
RCS pressure is 1000 psig and stable
RCS temperature is 508° F and slowly lowering
Total AFW flow is 650 gpm
PZR level is 32% and stable
RWST Level is 60% and slowly lowering
CCW Pump C has tripped
Which ONE of the following correctly completes the statements below?
lAW EOP-E-1, the NEXT require procedure transition is to
A.
B.
EOP-ES-1 .3, TRANSFER TO COLD LEG RECIRCULATION
C.
EOP-ES-1 .2, POST LOCA COOLDOWN AND DEPRESSURIZATION
D.
EOP-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION
Page 85 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
86
(1 point)
Given the following:
The plant is operating at 100% RIP
TME
EVENT
0800 yesterday
The feeder breaker from Emergency Bus E-1 to MCC-5 tripped
A loss of Instrument Bus 1 (lB-i) occurred
AOP-024, Loss of Instrument Bus, entered
0815 yesterday
WCC reports feeder breaker repair will take an extended amount of time
0820 yesterday
Auxiliary Operator transferred lB-i to MCC-8
0910 yesterday
Auxiliary Operator supplied power to MCC-5 from the DS bus
0100 today
Auxiliary Operator transferred lB-I from MCC-8 back to MCC-5
0805 today
Feeder breaker from Emergency Bus E-1 repaired.
Power restored to MCC-5 from E-1
Which ONE of the following correctly completes the statements below?
The Auxiliary Operator transfers lB-i power from MCC-8 back to MCC-5 in the
(1)
ALL Technical Specifications REQUIRED ACTION COMPLETION TIME(s)
2)
satisfied.
REFERENCE PROVIDED
A.
(1) Unit 2 Cable Spread Room
(2) were
B.
(1) Unit 2 Cable Spread Room
(2) were NOT
C.
(1)E1/E2Room
(2) were NOT
D.
(1)E1/E2Room
(2) were
Page 86 of 100
Question:
87
(1 point)
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Given the following:
A reactor trip and safety injection were required due to a C SGTR event
Coincident with the plant trip, a loss of the Startup Transformer occurred
The crew is in EOP-E-3, STEAM GENERATOR TUBE RUPTURE
The crew has just stopped the initial RCS cooldown at the target temperature
The OATC reports that CSFST-4, INTEGRITY is RED and observes the following:
FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK
A.
The CRS is required to immediately transition to FRP-P.1;
because the RED path on CSF-4 is VALID and the mitigation strategy in FRP-P.1 is of
higher priority than EOP-E-3
B.
The CRS is NOT requited to immediately transition to FRP-P.1;
because the RED path on CSF-4 is FALSE due to actions taken in EOP-E-3; later
steps will check for a VALID CSF-4 RED path
C.
The CRS is required to immediately transition to FRP-P.1;
because the RED path on CSF-4 is FALSE due to actions taken in EOP-E-3: based
on the events in progress, early steps in FRP-P.1 will return the crew to procedure
and step in effect
D.
The CRS is NOT required to immediately transition to FRP-P.1;
because the RED path on CSF-4 is FALSE due to actions taken in EOP-E-3; it will
ONLY be addressed when a transition out of EOP-E-3 to a subsequent Post-SGTR
procedure occurs
Which ONE of the following identifies how the CRS is required to proceed, AND the reason for
this action?
Page 87 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
88
(1 point)
Given the following sequence of events on October 9th 2017
Time
Conditions
08:30 AM
Automatic Rx Trip occurs.
08:50 AM
The crew exits EOP-ES-0.1, Reactor Trip Response, and transitions
to normal plant procedures. Plant is at NOT/NOP.
09:15 AM
Control Room is notified that all ventilation was lost to A Station
Battery. Station Management directs Maintenance to perform the
weekly surveillance on the A Station Battery.
10:05 AM
The Plant remains at NOT/NOP. Maintenance reports the following
for A Station Battery Pilot Cells:
Electrolyte level
% inch above minimum
2.06 Vdc
Corrected Specific Gravity
1 .205
Based on the given conditions, if A Station battery Pilot Cell parameters do NOT
change from Time = 10:05 indications, which ONE of the following is the LATEST time
allowed by Technical Specification to cool down to Tavg
200°F?
REFERENCE PROVIDED
A.
October 10th, 2017; at 10:05 PM
B.
October 1 1th, 2017; at 12:05 AM
C.
October 1 1th 2017; at 01:05 AM
D.
October 11111 2017; at 06:05 AM
Page 88 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
89
(1 point)
Given the following:
A plane crashed into the Intake Structure
The plant was manually tripped
The SUT tripped
The CRS has entered EPP-28, LOSS OF ULTIMATE HEAT SINK
ATTACHMENT 6, DEEPWELL COOLING
ATTACHMENT 7, ESTABLISHING CCW COOLING
Which ONE of the following correctly completes the statements below?
The MAXIMUM time the crew has to restore cooling to an EDG to preclude adverse
effects is
(1)
minutes.
In order to provide cooling to at least one EDG, the CRS is required to direct
ATTACHMENT
to be performed.
A.
(1)60
(2) 6
B.
(1)60
(2) 7
C.
(1)40
(2) 6
D.
(1)40
(2) 7
Page 89 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
90
(1 point)
Given the following:
The plant is at 100% RTP
Containment Purge is in service to reduce CV temperature for CV entry
R-12 is in alarm and confirmed to be VALID
R-1 2 is reading lower than the release permit allowed level
Which ONE of the following correctly completes the statements below?
An NRC report
(1)
required lAW AP-030, NRC REPORTING
REQUIREMENTS.
The CV purge
(2)
be restarted under the CURRENT permit.
REFERENCE PROVIDED
A.
(1)is
(2) may
B.
(1)is
(2) may NOT
C.
(1) is NOT
(2) may
D.
(1)is NOT
(2) may NOT
Page 90 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
91
(1 point)
Given the following:
GP-003, NORMAL PLANT STARTUP FROM HOT SHUTDOWN TO CRITICAL, is
in progress
The reactor is subcritical
The OATC is in the process of bringing the reactor critical
The licensed operator performing Attachment 10.3, CONTROL ROD
WITHDRAWAL CHECKLIST, of GP-003 reports that Bank D Control Rod Group
Step Counters indicate I Step when Bank C Group Step Counters indicate 128
steps
Which ONE of the following correctly completes the statements below?
Rod Control Bank Overlap ensures acceptable
lAW Technical Specification LCO 3.0.4, the reactor startup
(2)
continue.
A.
(1) shutdown margin
(2) can NOT
B.
(1) shutdown margin
(2) can
C.
(1) power peaking during control bank rod motion
(2) can NOT
D.
(1) power peaking during control bank rod motion
(2) can
Page 91 of 100
Robinson Nuclear Plant
ILC-1 7 RNP SRO NRC Examination
Question:
92
(1 point)
Given the following:
The plant is in Mode 6 with a core offload in progress
The CV Manipulator is moving a fuel assembly from core location H-8 to the CV
upender
Before the fuel assembly is lowered into the CV upender, the CV manipulator
operator accidently places the gripper switch to the DISENGAGE position
Subsequently;
The fuel assembly releases from the gripper while in the full up position and lands
on the CV upender
Which ONE of the following correctly completes the statements below?
The fuel assembly dropped due to a failure of
(1)
lAW OMM-OO1-18, OUTAGES, The refueling SRO
(2)
authorized to approve
bypassing refueling interlocks.
A.
(1) ONLY the Gripper Lock Interlock
(2) is
B.
(1) ONLY the Gripper Lock Interlock
(2) is NOT
C.
(1) BOTH the Gripper-Weight Indicator AND the Gripper Lock Interlocks
(2) is
D.
(1) BOTH the Gripper-Weight Indicator AND the Gripper Lock Interlocks
(2) is NOT
Page 92 of 100
Robinson Nuclear Plant
ILC-i 7 RNP $RO NRC Examination
Question:
93
(1 point)
Given the following:
The plant is at 400°F during a plant startup
LT-474, Steam Generator A Level Channel, has been removed from service for
maintenance per plant procedure.
Which ONE of the following identifies ALL the Tech Spec Limiting Conditions for
Operation (LCO(s)) that have required action(s) due to these conditions?
REFERENCE PROVIDED
A.
LCD 3.3.1, ONLY
B.
LCO 3.3.8, ONLY
C.
LCO 3.3.1 and LCD 3.3.3, ONLY
D.
LCO 3.3.3 and LCD 3.3.8, ONLY
Page 93 of 100
Robinson Nuclear Plant
ILC-i 7 RNP $RO NRC Examination
Question:
94
(1 point)
Given the following:
At 09:00 an ALERT Emergency Classification was declared
At 09:10 conditions degraded and a SITE AREA EMERGENCY was declared
The LATEST time that the INITIAL notification to the State and County Emergency
Organizations is required is
Li)
At 10:00 conditions degraded and a GENERAL EMERGENCY was declared
The LATEST time that the NRC is required to be notified of the upgrade to GENERAL
EMERGENCY is
(2)
A.
(1) 0915
(2) 1015
B.
(1) 0925
(2) 1015
C.
(1)0915
(2) 1100
D.
(1) 0925
(2) 1100
Page 94 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
95
(1 point)
Which ONE of the following correctly completes the statements below?
lAW FHP-003, FUEL ASSEMBLY MOVEMENT IN THE SPENT FUEL PIT, a Refueling
required to be established to load new fuel into the Spent Fuel Pool.
lAW FHP-003, permission is required from
(2)
to turn on the lights within the
Spent Fuel Pool in support of spent fuel movement within the Spent Fuel Pool.
A.
(1)is
B.
(1)is
(2) Reactor Engineering
C.
(1)isNOT
D.
(1)isNOT
(2) Reactor Engineering
Page 95 of 100
Robinson Nuclear Plant
ILC-i 7 RNP $RO NRC Examination
Question:
96
(1 point)
Given the following:
An outage is planned in which the plant is to be taken from MODE 1 to a complete
core off-load into the Spent Fuel Pit.
Which ONE of the following correctly completes the statements below?
The EARLIEST that the requirements of OMP-003, SHUTDOWN SAFETY FUNCTION
GUIDELINES, must be implemented is when
(1)
is entered.
The requirements of OMP-003
(2)
when the core is completely off-loaded to
the Spent Fuel Pit.
A.
(1)MODE3
(2) do NOT apply
B.
(1) MODE 3
(2) apply
C.
(1)MODE4
(2) apply
D.
(1)MODE4
(2) do NOT apply
Page 96 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
97
(1 point)
Given the following:
The plant is operating at 100% power
The crew performed OST-151-1, SAFETY INJECTION SYSTEM COMPONENTS
TEST
PUMP A with the following results:
On the initial stroke of 51-869, LOOPS B AND C HOT LEG INJECTION
SHUTOFF, the stroke time exceeded the CODE CRITERIA, but was less than
the LIMITING VALUE
During the run of the A SI Pump the operator recorded vibration level in the
REQUIRED ACTION range
Subsequently, the following sequence of events occur:
The A SI Pump is shutdown, placed under clearance, and repairs completed
The A SI Pump is retested lAW OST-151-J and vibrations are now in the ALERT
range
lAW OMM-015, OPERATIONS SURVEILLANCE TESTING, which ONE of the
following correctly completes the statements below?
For S1-869, OMM-015
allow the operators to immediately retest and
evaluate Sl-869 using the process defined in OMM-015.
Based on the retest, the A SI Pump is
A.
(1) does
(2) OPERABLE
B.
(1) does NOT
(2) OPERABLE
C.
(1) does
(2) inoperable
D.
(1) does NOT
(2) inoperable
Page 97 of 100
Robinson Nuclear Plant
ILC-i 7 RNP SRO NRC Examination
Question:
98
(1 point)
Which ONE of the following correctly completes the statement below?
lAW LCO 3.3.3. Bases, radiation monitor(s)
is/are required to be
OPERABLE to monitor for the potential of significant radiation releases, to provide
release assessment for use by operators in determining the need to invoke site
emergency plans, and to determine the type of high energy line break that has
occurred inside Containment.
A.
R-2, Containment
B.
R-1 1, Containment Particulate
C.
R-12, Containment Gas
D.
R-32A/B, Containment High Range
Page 9$ of 100
Robinson Nuclear Plant
ILC-1 7 RNP SRO NRC Examination
Question:
99
(1 point)
Given the following:
A reactor trip and safety injection has occurred from 100% RTP
Which ONE of the following correctly completes the statements below?
lAW OMM-022, EMERGENCY OPERATING PROCEDURES USERS GUIDE...
another licensed operator implements concurrent AOPs after EOP-E-0 immediate
actions
L11
(2)
apply during the performance of RED or
ORANGE FRPs.
AOP-034, SECURITY EVENTS
AOP-041, RESPONSE TO FIRE EVENT
A.
(1) have been completed and verified, ONLY
(2)do
B.
(1) have been completed and verified, ONLY
(2) do NOT
C.
(1) AND Attachment I of EOP-E-0 have been completed
(2)do
D.
(I) AND Attachment 1 of EOP-E-0 have been completed
(2) do NOT
Page 99 of 100
Robinson Nuclear Plant
ILC-i 7K/VP SRO NRC Examination
Question: 100
(1 point)
Which ONE of the following procedures does NOT contain a transition to SACRM-1,
SEVERE ACCIDENT CONTROL ROOM MANAGEMENT
INITIAL RESPONSE?
A.
EOP-ECA-O.O, LOSS OF ALL AC POWER
B.
FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING
C.
FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK
D.
I RESPONSE TO NUCLEAR POWER GENERATION
- ATWS
Page 100 of 100
Examination KEYfor: ILC-1 7 RNP SRO NRC Exami
Question
Answer
Nuniber
76
A
77
A
78
B
79
C
80
B
81
A
82
D
83
C
84
A
85
C
86
C
87
B
88
B
89
C
90
A
91
C
92
D
93
B
94
C
95
C
96
C
97
A
98
D
99
C
100
C
Printed 10/25/2017 10:28:24 AM
Paged of4
2017 H. B. ROBINSON NRC SRO Written Exam
Additional References Provided
In addition to the references provided for the RO Written Exam, SRO applicants were also
provided the following material on the day of examination:
1. Redacted copy of the hot EAL chart.
2. Redacted page 3.3-3 of Technical Specifications.
3. Non-redacted pages 3.8-19 through 3.8-34 of Technical Specifications.
4. Attachment 1, Immediate (One-Hour) Notifications to the NRC, of AP-030, NRC
REPORTING REQUIREMENTS, with page 1 of 11 intentionally deleted.
5. Attachment 2, Four Hour Notification to the NRC, of AP-030.
6. Attachment 3, Eight Hour Notifications to the NRC, of AP-030.
7. Redacted page 3.3-15 of Technical Specifications.
8. Redacted page 3.3-32 of Technical Specifications.
9. Redacted page 3.3-47 of Technical Specifications.