ML082110233
| ML082110233 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/30/2008 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-338/08-301, 50-339/08-301, ES-401 IR-08-301 | |
| Download: ML082110233 (129) | |
Similar Documents at North Anna | |
|---|---|
Category:License-Operator
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IR 05000338/2025301
See also: IR 05000338/2008301
Text
Final Submittal
(Blue Paper)
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Senior Operator Written Examination
aI L/ST OF It!/fs
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Name:
Site-Specific SRO Written Examination
Cover Sheet
u.s. Nuclear Regulatory Commission
Site-Specific SRO Written Examination
Applicant Information
Form ES-401-8
Date: June 24, 2008
Facility/Unit: North Anna/Units 1 &2
Region:
Start Time:
II
Reactor Type: Westinghouse
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 80.00 percent overall, with 70.00 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 80.00 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 Scores
/ -- / --
Points
Applicant's Grade
/ -- / --
Percent
NORTH ANNA 2008 RO/SRO WRITTEN EXAM
LIST OF KIA's & EXAM ANSWER KEY * FINAL
Page 1 of 3
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026 A4.0123
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029 K4.03 29
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055 EAI.06 37
056 AA2.72 38
057 02.4.45 39
058 AKL0140
059 Kl.02 41
060 AA2.05 42
061 G2.4.3 43
061 K2.0144
NORTH ANNA 2008 RO/SRO WRITTEN EXAM
LIST OF KIA's & EXAM ANSWER KEY * FINAL
Page 2 of 3
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A
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062 K3.03 46
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NORTH ANNA 2008 RO/SRO WRITTEN EXAM
LIST OF KIA's & EXAM ANSWER KEY* FINAL
Page 3 of 3
89
056 G2.2.3689
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NAME
_
North Anna Power Station
2008 SRO Exam
1.
Given the following:
During a Unit 1 load reduction for 1-PT-34.3, Turbine Valve Freedom Test, the
following alarm is received:
1A-D1, ROD CONTROL URGENT FAILURE
The Ramp has been held and power is approximately 93%.
Tave is 2.50F higher than Tref.
Investigation reveals that a Logic Cabinet Oscillator Failure has occurred.
Which ONE of the following describes how this failure will affect the Rod Control
System, including the required action in accordance with the annunciator response
procedure?
A. Rod motion is NOT inhibited in 'Bank Select'; adjust Turbine load or use rods in
Bank Select to match Tave to Tref.
B. All rod motion is inhibited; adjust Turbine load ONLY to match Tave to Tref.
C. All rod motion is inhibited; adjust Turbine load or adjust RCS boron concentration to
match Tave to Tref.
D. Rod motion is NOT inhibited in 'Bank Select'; use rods in Bank Select ONLY to
match Tave to Tref.
1
North Anna Power Station
2008 SRO Exam
2.
Given the following:
Unit 1 cooldown and depressurization is in progress for refueling.
RCS temperature is 195 degrees F and slowly decreasing.
RCS pressure is 360 psig and slowly decreasing.
"A" and "C RCPs are running.
RHR is in service.
The crew observes the following indications:
Annunciator 1C-G8, RCP 1A-B-C SEAL LEAK La FLOW is received.
Sealleakoff flow on all three RCPs is approximately 0.7 gpm and slowly
decreasing.
All RCP Pump Radial Bearing temperatures are approximately 130 degreesF
and stable.
All RCP Seal Water outlet temperatures are approximately 160 degrees F and
stable.
RCP standpipe alarms are all CLEAR.
Which ONE of the following is correct concerning operation of 1-CH-HCV-1307, RCP
Seal Bypass Isolation Valve?
A. Maintain closed and de-energized to address Appendix-R concerns.
B. Maintain closed and de-energized due to the potential for RCP seal damage.
C. Energize and open the valve to prevent overheating the #1 seals.
D. Energize and open the valve to prevent overheating pump radial bearing.
2
North Anna Power Station
2008 SRO Exam
3.
Which ONE of the following describes a NORMAL Unit 2 BAST alignment?
A. 'C' BAST through 1-CH-P-2D to Unit 2 Boric Acid Filter to Unit 2 BIT/Blender.
B. 'A' BAST through 1-CH-P-2A to Unit 2 Boric Acid Filter to Unit 2 BIT/Blender.
C. 'C' BAST through 1-CH-P-2D through recirc valve 1-CH-HCV-11 04 ONLY and back
to 'C' BAST.
D. 'B' BAST through 1-CH-P-2A to Unit 2 Boric Acid Filter to Unit 2 BIT/Blender.
3
North Anna Power Station
2008 SRO Exam
4.
Given the following:
Unit 1 is in Mode 6.
The unit has been shutdown for 11 days.
Cavity level is 22 feet above the reactor vessel flange.
RCS temperature is 109 degrees F.
RHR Loop 1A is in service.
Which ONE of the following is the MINIMUM RHR flow requirement based on these
plant conditions, including the reason for this minimum flow requirement, in accordance
with 1-0P-14.1, Residual Heat Removal?
A. 2500 GPM; prevents flow induced chatter on SI Accumulator check valves.
B. 3000 GPM; satisfies Technical Specification minimum flow requirements in Mode 6.
C. 3000 GPM; prevents flow induced chatter on SI Accumulator check valves.
D. 2500 GPM; satisfies Technical Specification minimum flow requirements in Mode 6.
4
North Anna Power Station
2008 SRO Exam
5.
Given the following:
Unit 1 is in Mode 4 with a plant cooldown to Mode 5 in progress.
RCS Pressure is 720 psig.
RCS temperature is 325°F.
Which ONE of the following states the power supply to 1-SI-MOV-1865A, 'A'
Accumulator Discharge Isolation Valve, and its required breaker position for the current
plant conditions?
480 Volt MCC...
A.
1J1; breaker is closed.
B. 1H1; breaker is open.
C. 1H1; breaker is closed.
D. 1J1; breaker is open.
5
North Anna Power Station
2008 SRO Exam
6.
Given the following:
Unit 1 is in Mode 3.
PRT level is 740/0 and INCREASING SLOWLY.
PRT pressure is 12 psig and INCREASING SLOWLY.
PRT temperature is 132°F and INCREASING SLOWLY.
The following annunciators are LIT:
1B-H1, PRZ RELIEF TK HI TEMP
1B-G2, PRZ SAFETY W
LINE HI TEMP
1B-H2, PRZ POWER RELIEF LINE HI TEMP
Acoustic monitor indications are NORMAL.
Which ONE of the following identifies the cause of the conditions above, and includes
the method used to identify the affected component in accordance with annunciator
response procedures?
A. Pressurizer PORV leaking by;
Check tailpipe temperature indication to determine which PORV is leaking.
B. Pressurizer Safety Valve leaking by;
Check tailpipe temperature indication to determine which Safety Valve is leaking.
C. Pressurizer PORV leaking by;
Close block valves one-at-a-time to determine which PORV is leaking.
D. Pressurizer Safety Valve leaking by;
Check tailpipe temperatures with a contact pyrometer to determine which Safety
Valve is leaking.
6
North Anna Power Station
2008 SRO Exam
7.
Given the following:
Unit 1 was initially at 100% power at the end of core life.
Fuel failures have resulted in increased RCS activity (still within Tech Spec
limits).
A spurious Safety Injection (SI) occurred.
One train of SI failed to reset from the control room.
Multiple PRZR PORV lifts occurred during the recovery.
PRT pressure is 115 psig.
Which ONE of the following identifies the current conditions in the Containment
including the raditation monitor indications in the Main Control Room?
A. Containment Sump level constant;
Containment Particulate and Gaseous Radiation Monitors constant.
B. Containment Sump level increasing;
Containment Particulate and Gaseous Radiation Monitors increasing.
C. Containment Sump level increasing;
Containment High Range radiation Monitors constant.
D. Containment Sump level increasing;
Containment High Range Radiation Monitors increasing.
7
North Anna Power Station
2008 SRO Exam
8.
Given the following:
A reactor trip has occurred on Unit 1.
Safety Injection is actuated.
RCS pressure is 1200 psig.
Containment pressure has peaked at 16 psia and is slowly trending down.
Pressurizer level is 100%
The crew is performing 1-E-0, Reactor Trip or Safety Injection.
Which ONE of the following describes the method used to control RCS temperature
and the approximate Main Steam pressure maintained?
A. Condenser Steam Dumps; 1035 psig.
D. Condenser Steam Dumps; 1005 psig.
8
North Anna Power Station
2008 SRO Exam
9.
Given the following:
Unit 1 is at 100% power.
CC Pump 1A is running and CC Pump 1B is in standby.
4160 V Bus 1H normal feeder is inadvertantly opened.
Which ONE of the following describes the AUTOMATIC operation of CC Pumps for this
event?
A. CC Pump 1B starts 15 to 20 seconds after Bus 1H is reenergized; CC Pump 1A
does NOT re-start.
B. CC Pump 1B starts when Bus 1H is deenergized; CC Pump 1A starts as soon as
Bus 1H is reenergized.
C. CC Pump 1B starts 15 to 20 seconds after Bus 1H is reenergized; CC Pump 1A
starts 15 to 20 seconds after Bus 1H is reenergized.
D. CC Pump 1B starts when Bus 1H is deenergized; CC Pump 1A restarts 15 to 20
seconds after Bus 1H is reenergized.
9
North Anna Power Station
2008 SRO Exam
10.
Given the following:
A LOCA has occurred.
The crew is performing 1-E-1, Loss of Reactor or Secondary Coolant.
The following conditions exist:
All SG pressures - 930 psig and slowly trending down.
All SG levels - being controlled at 42%
NR.
PZR level - off-scale high.
Containment Pressure - 23 psia.
RWST level - 32% and decreasing at 1% every 4 minutes.
RCS pressure - 1000 psig and stable.
Core Exit TCs - 500 degrees F.
RVLIS Full Range indication 74%.
Based on these indications, which ONE of the following procedure entry requirements
are met?
A. 1-ES-1.3, Transfer to Cold Leg Recirculation
B. 1-ES-1.2, Post-LOCA Cooldown and Depressurization
C. 1-ES-1.1, SI Termination
D. 1-FR-C.2, Response to Degraded Core Cooling
10
North Anna Power Station
2008 SRO Exam
11.
Given the following:
The RCS is solid in Mode 5.
The crew is preparing to draw a bubble in accordance with 1-0P-1.1, Unit
Startup From Mode 5 At Less Than 140 Degrees F To Mode 5 At Less Than
200 Degrees F.
PZR pressure is approximately 325 psig.
PZR temperature is 335 degrees F.
RCS temperature is 180 degrees F.
Assuming PZR Heatup rate is at the administrative limit of 1-0P-1.1, approximately
how long will it take to reach saturation conditions in the pressurizer, and what action
will be required when saturation conditions are reached?
A. 60 minutes; the letdown backpressure control valve potentiometer setpoint will be
increased.
B. 30 minutes; letdown flow will be manually increased.
C. 60 minutes; letdown flow will be manually increased.
D. 30 minutes; the letdown backpressure control valve potentiometer setpoint will be
increased.
11
North Anna Power Station
2008 SRO Exam
12.
Given the following:
A Large Break LOCA has occurred on Unit 1.
The crew has completed transition to 1-ES-1.3, Transfer to Cold Leg
Recirculation.
RWST level is 14°A>.
Given these current plant conditions, which ONE of the following identifies the required
ECCS and Charging pump alignment after the initial swapover to Cold Leg
Recirculation is performed in accordance with 1-ES-1.3?
A. Low Head SI Pump flowing to Charging pumps ONLY; Charging Pump suction from
LHSI Pumps.
B. Low Head SI Pump suction from Containment Sump; Charging Pump suction from
RWST.
C. Low Head SI Pump suction from Containment Sump; Charging Pump suction from
LHSI Pumps.
D. Low Head SI Pump flowing to Charging pumps ONLY; Charging Pump suction from
RWST.
12
North Anna Power Station
2008 SRO Exam
13.
Given the following:
A plant load reduction is in progress.
Turbine First Stage Pressure Channel, 1-MS-PT-1446, sticks at 500~.
Reactor power is currently 8%.
Which ONE of the following identifies the RPS permissive affected by this transmitter
failure, including the MINIMUM number of RCPs, which if lost, would cause a Reactor
Trip?
A. P-8 cannot be satisfied; the reactor would trip on loss of 2 RCPs.
B. P-7 cannot be satisfied; the reactor would trip on loss of ONLY 1 RCP.
C. P-7 cannot be satisfied; the reactor would trip on loss of 2 RCPs.
D. P-8 cannot be satisfied; the reactor would trip on loss of ONLY 1 RCP.
13
North Anna Power Station
2008 SRO Exam
14.
An event has occurred on Unit 1 resulting in core damage.
Containment pressure peaked at 28 psia.
Containment radiation peaked at 2E+5R/hr.
Current Plant parameters are as follows:
RCS temperature is slowly trending down.
All SGs are 150/0 Narrow Range and rising.
AFW flow to each SG is 150 gpm.
Containment pressure is 16 psia and slowly trending down.
Containment radiation is 1E+4R/hr and slowly trending down.
Which ONE of the following identifies the AFW flow requirements in accordance with
1-E-0, Reactor Trip or Safety Injection, and the Adverse Containment criteria?
A. AFW may be reduced to 50 gpm to each SG since Containment pressure has
decreased to the current value.
B. AFW may be reduced to 50 gpm to each SG since Containment radiation has
decreased to the current value.
C. Total AFW flow must be maintained> 340 gpm because of the Containment
pressure transient.
D. Total AFW flow must be maintained> 340 gpm because of the Containment
radiation transient.
14
15.
North Anna Power Station
2008 SRO Exam
The Unit is at 100% power.
A failure of a semi-automatic tester board has occurred in the Solid State
Protection System resulting in a General Warning condition.
Which ONE of the following describes how the system is designed for the operator to
identify the condition and determine the affected Train?
A. A common Safeguards Trouble annunciator is provided in the control room;
RED GENERAL WARNING light in the affected train's logic cabinet will be
extinguished.
B. Train-specific Safeguards Trouble annunciators are provided in the control room;
RED GENERAL WARNING light in the affected train's logic cabinet will be
extinguished.
c. A common Safeguards Trouble annunciator is provided in the control room;
RED GENERAL WARNING light in the affected train's logic cabinet will be LIT.
D. Train-specific Safeguards Trouble annunciators are provided in the control room;
RED GENERAL WARNING light in the affected train's logic cabinet will be LIT.
15
North Anna Power Station
2008 SRO Exam
16.
Given the following:
Unit 1 is at 100% power.
The following alarm is received:
1C-G7, RCP 1A-B-C SEAL LEAK HI FLOW
RCP 1B Seal Leakoff flow indicates 6 GPM.
RCP 1B No.1 Seal DP indicates 220 psid and stable.
Annunciator 1C-G2, RCP 1B STANDPIPE HI LEVEL is NOT LIT.
Sealleakoff has lowered on RCP 1A and 1C.
Seal Return temperature is rising slowly.
Which ONE of the following identifies the RCP seal problem, including the required
actions in accordance with 1-AP-33.1, Reactor Coolant Pump Seal Failure?
A. RCP #1 seal;
monitor RCP bearing temperatures and initiate a plant shutdown to Hot Standby.
B. RCP #2 seal;
trip the reactor, trip the RCP, and isolate sealleakoff within 5 minutes.
C. RCP #1 seal;
trip the reactor, trip the Rep, and isolate seal leakoff within 5 minutes.
D. RCP #2 seal;
monitor RCP bearing temperatures and initiate a plant shutdown to Hot Standby.
16
17.
North Anna Power Station
2008 SRO Exam
The Unit is currently at 100% and stable. Control group heaters are operating
properly and one additional set of PRZR backup heaters are locked on.
Which ONE of the following malfunctions can occur WITHOUT affecting PRZR heater
status regardless of the position of the Pressurizer Level Control selector switch?
A. PRZR level ChanneI1-RC-LT-460 failing LOW.
B. PRZR level Channel 1-RC-LT-459 failing HIGH.
C. PRZR level ChanneI1-RC-LT-459 failing LOW.
D. PRZR level ChanneI1-RC-LT-460 failing HIGH.
17
North Anna Power Station
2008 SRO Exam
18.
Given the following:
A LOCA has occurred on Unit 1.
1A Charging Pump is tripped.
1B Charging Pump is running.
BOTH LHSI Pumps are tripped.
RCPs are running.
RCS pressure is 1600 psig and lowering.
Containment pressure peaked at 21 psia and is now slowly trending down.
Core Exit TICs are 545 degrees F.
Which ONE of the following identifies the requirement for operation of RCPs in
accordance with 1-E-0, Reactor Trip or Safety Injection, including the reason?
A.
Leave RCPs running because forced circulation provides sufficient core cooling.
B. Stop RCPs because continued operation will result in damage to the RCPs due to
loss of cooling water.
C. Stop RCPs because an inadequate core cooling condition could develop if RCPs
were tripped or lost later in the event.
D. Leave RCPs running because ECCS flow is inadeq-uate to ensure adequate core
cooling.
18
North Anna Power Station
2008 SRO Exam
19.
Given the following:
Unit 1 is at 1000/0 power.
The Mechanical Chiller has tripped and cannot be restarted.
The crew enters 1-AP-35, Loss of Containment Air Recirculation Cooling.
Which ONE of the following identifies the Containment temperature that requires
entering the action statement for TS 3.6.5, Containment Air Temperature, and also
identifies the required actions to be taken for these plant conditions in accordance with
1-AP-35?
A. 115 degrees F; ensure Containment Air Recirc Fans are running with backdraft
dampers closed.
B. 105 degrees F; ensure steam chiller running or align Service Water to Containment
Air Recirc Fans.
C. 105 degrees F; ensure Containment Air Recirc Fans are running with backdraft
dampers closed.
D. 115 degrees F; ensure steam chiller running or align Service Water to Containment
Air Recirc Fans.
19
North Anna Power Station
2008 SRO Exam
20.
Given the following:
Unit 1 is at 100°Jlc> power following a refueling outage.
The crew has isolated a Letdown line leak in accordance with 1-AP-16,
Increasing Primary Plant Leakage.
The crew is preparing to place Excess Letdown in service.
Excess Letdown will be aligned to the VCT.
Which ONE of the following identifies 1) an Excess Letdown Lineup restriction and 2)
the reason why reactor power must be monitored when placing excess letdown in
service in accordance with 1-0P-8.5, Operation of Excess Letdown?
A. Flow through ONLY one loop drain to prevent the possibility of bypassing 81 flow to
the 2 intact loops in a design basis accident;
a dilution may occur due to lower boron concentrations in the Excess Letdown
piping.
B. Excess Letdown Pressure must NOT exceed 75 psig to prevent overpressurizing
the VCT;
a dilution may occur due to lower boron concentrations in the Excess Letdown
piping.
C. Excess Letdown Pressure must NOT exceed 75 psig to prevent overpressurizing
the VCT;
a boration may occur due to higher boron concentrations in the Excess Letdown
piping.
D. Flow through ONLY one loop drain to prevent the possibility of bypassing 81 flow to
the 2 intact loops in a design basis accident;
a boration may occur due to higher boron concentrations in the Excess Letdown
piping.
20
North Anna Power Station
2008 SRO Exam
21.
Both Units are at 100%.
A fault on the Unit 2B station service bus results in a Main Generator Lockout
and Reactor Trip.
All Unit 2 Station Service Busses are deenergized due to the feeder breaker to
2B Station Service bus failing to open on the fault.
Which ONE of the following describes the status of Containment cooling to the Units?
A. Containment Air Recirc Fans remain running on BOTH Units; Chilled water flow to
Containment Air Recirc Fans is lost on Unit 2 ONLY.
B. Containment Air Recirc Fans remain running on BOTH Units; Chilled water flow to
Containment Air Recirc Fans is lost on BOTH Units.
C. Containment Air Recirc Fans trip on Unit 2; Chilled water flow to Containment Air
Recirc Fans is lost on Unit 2 ONLY.
D. Containment Air Recirc Fans trip on Unit 2; Chilled water flow to Containment Air
Recirc Fans is lost on BOTH Units.
21
North Anna Power Station
2008 SRO Exam
22.
Given the following:
Unit 1 has just entered Mode 4 with cooldown to Mode 5 in progress.
RHR Pump 1A is in service.
The OATC notes the following:
RHR Pump 1A motor amps indicate 10 and stable.
1-RH-FCV-1605 in automatic indicates 1000/ 0 demand.
Which ONE of the following identifies the status of the 1-RH-FCV-1605, RHR Heat
EXchanger Bypass Valve AND predicts the trend on Core Exit TCs?
A.
1-RH-FCV-1605 operating as designed;
Core Exit TCs stable.
B. 1-RH-FCV-1605 failed;
Core Exit TCs lowering.
C. 1-RH-FCV-1605 failed;
Core Exit TCs increasing.
D. 1-RH-FCV-1605 operating as designed;
Core Exit TCs increasing.
22
North Anna Power Station
2008 SRO Exam
23.
Given the following:
A reactor trip and safety injection has occurred.
RCS pressure is 1000 psig and stable.
Containment pressure is 23 psia and rising slowly.
The crew is performing 1-E-0, Reactor Trip or Safety Injection.
Which ONE of the following describes the appropriate operator action and the
SEQUENCE of the action required?
A. COA is not required, however Quench Spray is required; start Quench Spray
Pumps and then open Quench Spray discharge valves.
B. COA is required; manually actuate COA, stop RCPs, verify Quench Spray running,
and verify Containment Isolation Phase B.
C. COA is not required, however Quench Spray is required; open Quench Spray
Discharge Valves and then start Quench Spray Pumps.
O. COA is required; manually actuate COA, stop CC pumps, verify Quench Spray
running, verify Containment Isolation Phase B, and stop RCPs.
23
North Anna Power Station
2008 SRO Exam
24.
Given the following:
The unit is operating at 100%
power.
CC Surge Tank level indication on 1-CC-LI-101 is 500/0 and lowering.
Which ONE (1) of the following is a possible source of the leak and the source of water
for maintaining CC System inventory?
A. Non-Regenerative Heat Exchanger; Condensate System
B. Non-Regenerative Heat Exchanger; PG water
C. 1A CC Heat Exchanger; Condensate System
D. 1A CC Heat Exchanger; PG water
24
North Anna Power Station
2008 SRO Exam
25.
Given the following on Unit 1:
Reactor Trip due to a LOCA.
Safety Injection was actuated 11 minutes ago.
COA was automatically actuated 7 minutes ago.
RCS pressure is 1125 psig.
RWST level is 720/0 and lowering.
Which ONE of the following describes the operational status of Inside Recirculation
Spray Pump 1-RS-P-1 B?
A. NOT running; power is available directly from 4160 volt bus 1J.
B. Running; power is supplied directly from 480 volt bus 1J1.
C. Running, power is supplied directly from 4160 volt bus 1J.
O. NOT running; power is available directly from 480 volt bus 1J1.
25
North Anna Power Station
2008 SRO Exam
26.
Given the following:
Unit 1 is operating at 100% power.
An instrument failure causes PORV 1-RC-PCV-1455C to lift.
RCS Pressure is recovering at a much slower rate than expected.
The operator closes the PORV Block Valve, 1-RC-MOV-1536, and pressure is
now 2100 psig and increasing as expected.
All other equipment appears to be operating normally.
Which ONE (1) of the following describes the action(s) required within ONE hour in
accordance with Technical Specifications?
A. Maintain closed and maintain power to 1-RC-MOV-1536.
B. Restore RCS pressure to within limits of the COLR.
C. Verify P-11 interlock is in required state for existing unit condition ..
D. Maintain closed and remove power from 1-RC-MOV-1536.
26
North Anna Power Station
2008 SRO Exam
27.
Given the following:
Unit 1 was initially at 1000/0.
Unit 1 experienced a large break LOCA
The crew placed 1-HC-HC-1, Hydrogen Recombiner in service on Unit 1
Containment.
The Recombiner tripped within 5 minutes and could not be restarted.
Hydrogen concentration is now 3°~.
Given these plant conditions which ONE of the following identifies the required
operator response in accordance with 1-E-1, Loss of Reactor or Secondary Coolant?
A. Place 2-HC-HC-1, Hydrogen Recombiner, in service on Unit 1 Containment.
B. Place 1-HC-F-1, Containment Atmosphere Purge Blower, in service on Unit 1
Containment.
C. Place 2-HC-F-1, Containment Atmosphere Purge Blower, in service on Unit 1
Containment.
D. Vent Unit-1 containment through the Auxiliary Building Iodine Filters.
27
North Anna Power Station
2008 SRO Exam
28.
During an ATWS at 100DA> Reactor Power, EOL conditions, which ONE of the following
actions will insert the MOST negative reactivity within the FIRST 30 seconds of the
ATWS?
A. Initiation of Emergency Boration
B. Manual Turbine Trip
C. Automatic Control Rod Insertion
D. Manual Control Rod Insertion
28
North Anna Power Station
2008 SRO Exam
29.
Given the following:
Both units are in Mode 5.
Containment.pur~e is in progress on each unit in preparation for Containment
entrv.wrlh bo+ll pvr?>e stJpply *to..i1S' I'Vf\\(\\ ,Yl3'
Unit 1 Manipulator Crane Area Radiation Monitor RM-162 indication is rising.
Unit 1 Containment Particulate and Gaseous Radiation Monitors, RM-159 and
160 are in alarm.
Unit 2 containment conditions are normal.
Which ONE of the following predicts the final status of Containment Purge after ALL
automatic actuations have taken place?
A. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B NOT running;
Containment Purge Supply isolation valves closed on BOTH units.
B. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B both running;
Unit 1 Containment Purge Supply isolation valves close.d;
Unit 2 Containment Purge Supply isolation valves open.
C. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B NOT running;
Unit 1 Containment Purge Supply isolation valves closed;
Unit 2 Containment Purge Supply isolation valves open.
D. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B both running;
Containment Purge Supply isolation valves closed on BOTH units.
29
North Anna Power Station
2008 SRO Exam
30.
Given the following conditions:
A reactor startup is in progress and operators have just completed a rod pull.
Both Intermediate Range channels indicate approximately 3 E -11 amps and
trending up.
Source Range Channel N-31 indicates 1X103 CPS and is trending down slowly.
Source Range Channel N-32 indicates approximately 6X103 CPS and trending
up slowly.
Which ONE of the following describes the required operator response in accordance
with 1-AP-4.1, Malfunction of Source Range Nuclear Instrumentation, and the reason
for the response?
A. Suspend the reactor startup; due to insufficient overlap between Source Range and
Intermediate Range channels.
B. Continue the reactor startup; the operable Source Range channel is adequate to
provide protection against a boron dilution event.
C. Suspend the reactor startup; with only one Source Range channel operable, there
is inadequate protection against an uncontrolled rod withdrawal.
D. Continue the reactor startup; the operable Source Range channel is adequate to
provide protection against an uncontrolled rod withdrawal.
30
31.
North Anna Power Station
2008 SRO Exam
Operators are performing a blended make-up to the Spent Fuel Pool (SFP)
following completion of cask loading operations.
A calibration error results in 1-CH-FT-1114, PG Water to blender flow transmitter
indicating less than the actual flowrate.
Which ONE of the following predicts the effect on boron concentration of the blended
flow based on these plant conditions, and identifies the Technical Specification
minimum required boron concentration for the SFP?
A. Boron concentration of the blended flow will be greater than the calculated value;
2600 ppm.
B. Boron concentration of the blended flow will be less than the calculated value;
2500 ppm.
C. Boron concentration of the blended flow will be greater than the calculated value;
2500 ppm.
D. Boron concentration of the blended flow will be less than the calculated value;
2600 ppm.
31
North Anna Power Station
2008 SRO Exam
32.
Given the following:
Unit 1 is in Mode 6 with Core offload in progress.
A fuel assembly becomes visibly damaged when removed from the core.
Containment radiation is rising slowly.
The assembly is returned to its location.
Containment evacuation has been initiated.
Which ONE of the following identifies 1) the expected indications and 2) the crew's
response in accordance with O-AP-5.2, MGP Radiation Monitoring System?
A. Vent Stack 'B' Radiation Monitor indication increases;
Verify Containment Purge Exhaust automatically isolates when Vent Stack 'B'
Radiation Monitor exceeds alarm setpoint.
B. Vent Stack 'A' Radiation Monitor indication increases;
Verify Containment Purge Exhaust automatically isolates when Vent Stack 'A'
Radiation Monitor exceeds alarm setpoint.
C. Vent Stack 'A' Radiation Monitor indication increases;
Manually divert Containment Purge Exhaust through the Auxiliary Building Iodine
Filters
D. Vent Stack 'B' Radiation Monitor indication increases;
Manually divert Containment Purge Exhaust through the Auxiliary Building Iodine
Filters.
32
North Anna Power Station
2008 SRO Exam
33.
Which ONE of the following describes the reason for equalizing Main Steam pressure
when opening a Main Steam NRV that has been closed?
A. Prevent damage to valve internals due to excessive DP when opening the NRV.
B. Prevent excessive swell of SG volume.
C. Prevent themal overload of breaker for NRV due to excessive DP when opening the
NRV.
D. Prevent inadvertent Hi Steam Line Differential Pressure SI.
33
North Anna Power Station
2008 SRO Exam
34.
Given the following:
Unit 1 is at 100 % power.
Rod Control is in MAN UAL.
All other controls are in AUTO.
A Turbine control valve failure results in a load rejection.
Tavg - Tref deviation indicates 11 degrees F.
1M-D4, STEAM DUMP ARMED, is illuminated.
Which ONE of the following describes Steam Dump response?
A. Two banks of steam dumps are modulating open;
Two banks of steam dumps are closed.
B. One bank of steam dumps is tripped open;
One bank of steam dumps is modulating open.
C. Four banks of steam dumps are tripped open.
D. Two banks of steam dumps are tripped open;
One bank of steam dumps is modulating open.
34
North Anna Power Station
2008 SRO Exam
35.
Given the following:
Reactor power is 75°A>.
1B MFW Pump is out of service for pump coupling repairs.
The following alarms are received:
1F-A4, MAIN FD PPS DISCH HDR LO PRESS
1F-A5, MAIN FD PP 1A-1B-1C AUTO TRIP
1F-F1/F2/F3, SG 1N1 B/1C LEVEL ERROR
1F-D1/D2/D3, STM GEN 1A11 B/1C FW<STrvl FLOW CH III-IV
The BOP determines that 1C MFW Pump is tripped.
The crew enters 1-AP-31, Loss of Feedwater.
Which ONE of the following describes the action required, and reason for the action?
A. Reduce load; prevent operating MFW pump motor windings from overheating due
to excessive current.
B. Trip the reactor; prevents damage to operating Main Feedwater Pump due to pump
runout flow and cavitation.
C. Trip the reactor; prevents a challenge to the Reactor Protection System from loss of
secondary heat sink.
D. Reduce load; reduces steam flow to within the capacity of the operating MFW
pump.
35
36.
North Anna Power Station
2008 SRO Exam
Initial Conditions:
A Steam Generator Tube Leak is occurring on Unit 1.
The crew is entering 1-AP-24, Steam Generator Tube Leak.
Condenser Air Ejector Radiation Monitor 1-SV-RM-121 is in Hi-Hi alarm.
Current conditions:
Safety Injection is actuated.
The crew is performing actions of 1-E-O, Reactor Trip or Safety Injection.
Which ONE of the following describes the alignment of the Condenser Air Ejector
steam supply and exhaust for the current conditions?
.
A. Exhaust isolated on Phase A isolation; steam supply to air ejectors isolated on
Phase A isolation.
B. Exhaust diverted to Containment on Phase A isolation; steam supply to air ejectors
isolated on Phase A isolation.
C. Exhaust diverted to Containment on HI-HI radiation; steam supply to air ejectors
isolated on HI-HI radiation.
D. Exhaust isolated on HI-HI radiation; steam supply to air ejectors isolated on HI-HI
radiation.
36
North Anna Power Station
2008 SRO Exam
37.
Given the following:
A loss of all AC Power has occurred.
The crew is performing actions of 1-ECA-O.O, Loss of All AC Power.
1H EDG has failed and CANNOT be restarted.
The crew is performing 1-ECA-O.O, Attachment 4, Attempting to restore power to
1H (1J) Emergency Bus.
Attempts to start EDG 1J are in progress.
RCP Seal Water Outlet temperature is 200°F and rising at 20F per minute.
Which ONE of the following describes the action required in accordance with ECA-O.O?
A.
Place 1J EDG in MANUAL-LOCAL, press EMER GEN Alarm & Shutdown RESET
Button, and verify Shutdown Relay Status Light is lit. After one minute, place 1J
EDG in MANUAL - REMOTE and determine if the EDG starts.
B. Place Charging Pumps in PTL prior to attempting to start 1J EDG in MANUAL -
LOCAL.
C. Perform Attachment 3, RCP seal isolation, prior to attempting to start 1J EDG in
MANUAL- LOCAL.
D. Place 1J EDG in MANUAL-REMOTE, press EMER GEN Alarm & Shutdown
RESET Button, and verify Shutdown Relay Status Light is lit. After one minute,
place 1J EDG in MANUAL - LOCAL and determine if the EDG starts.
37
North Anna Power Station
2008 SRO Exam
38.
Given the following:
AFW pump 1-FW-P-2 is tagged out to replace the overspeed trip tappet.
Unit 1 reactor trip from 100 % power.
Severe weather causes a Loss of Off-Site power.
An electrical fault on 1H Bus has caused a bus lockout.
Which ONE of the following describes the response of the AFW System during this
event?
A.
1-FW-P-3B starts as soon as the 4160 Volt emergency bus is energized;
B. 1-FW-P-3B starts approximately 20 seconds after the 4160 Volt emergency bus is
energized;
C. 1-FW-P-3B starts approximately 20 seconds after the 4160 Volt emergency bus is
energized;
D. 1-FW-P-3B starts as soon as the 4160 Volt emergency bus is energized;
38
North Anna Power Station
2008 SRO Exam
39.
The Unit is in MODE 3 preparing to startup.
Loss of vital bus 1-1 occurred and power has not yet been restored.
Station Emergency Manager just declared a Notification of Unusual Event.
Which ONE of the following describes the correct response and required notifications?
A. Monitor RCP temperatures due to loss of CC flow;
Notification of State and Local authorities is required within the next 15 minutes.
B. Monitor RCP temperatures due to loss of CC flow;
Notification of State and Local authorities is required within the next 60 minutes.
C. Monitor SG PORVs due to loss of condenser steam dumps;
Notification of State and Local authorities is required within the next 15 minutes.
D. Monitor SG PORVs due to loss of condenser steam dumps;
Notification of State and Local authorities is required within the next 60 minutes.
39
North Anna Power Station
2008 SRO Exam
40.
Given the following:
Unit 1 is at 100 % power.
All DC Bus voltages are approximately 131 VDC.
The following alarm is received in the control room:
1H-B3, BATTERY CHGR 1-111 TROUBLE
Battery Charger 1-111 DC Output breaker has tripped and CANNOT be reset.
DC Bus 1-111 voltage is 118 volts and lowering.
Which ONE of the following describes the action that will be taken to restore DC Bus
1-111 in accordance with 1-0P-26.4.3, Main Station Swing Battery Chargers 1C-1 and
1C-II Operation?
A. Place Swing Battery Charger 1C-I in service with the NORMAL/EQUALIZE switch in
EQUALIZE.
B. Place Swing Battery Charger 1C-II in service with the NORMAL/EQUALIZE switch
in NORMAL.
C. Place Swing Battery Charger 1C-II in service with the NORMAL/EQUALIZE switch
in EQUALIZE.
D. Place Swing Battery Charger 1C-I in service with the NORMAL/EQUALIZE switch in
NORMAL.
40
North Anna Power Station
2008 SRO Exam
41.
Given the following:
The plant is at 25°h power.
A Condensate header rupture occurs, and the following conditions are present:
All Main Feedwater pumps tripped.
10 seconds later SG levels are 300/0 narrow range and lowering.
Reactor power remains at 25°h.
Which ONE of the following describes the operation of the Reactor Protection System
and the Auxiliary Feedwater (AFW) Pumps for this condition?
A. A reactor trip setpoint has NOT been exceeded; AFW Pumps are NOT running.
B. A reactor trip setpoint has been exceeded; AFW Pumps are running.
C. A reactor trip setpoint has NOT been exceeded; AFW Pumps are running.
D. A reactor trip setpoint has been exceeded; AFW Pumps are NOT running.
41
North Anna Power Station
2008 SRO Exam
42.
Given the following:
Release of Waste Gas Decay Tank 1B is in progress.
1-GW-RI-178-1, Process Vent Normal Range Monitor, indication is rising.
1-GW-RI-178-2, Process Vent High Range Monitor, indication is just coming on
scale.
The following alarms are received:
2B-A5, PROCESS VENT VNT STACK A&B LOW RAD MON
ALERT/RAD
2B-B5, PROCESS VENT VNT STACK A&B HI HI RADIATION
Which ONE of the following describes the status of the Waste Gas Decay Tank
release lineup?
A. 1-GW-FCV-101 AND 1-GW-PCV-117 closed when 1-GW-RI-178-1 HI radiation
alarm was received.
B. 1-GW-FCV-101 remained open UNTIL 1-GW-RI-178-2 HI radiation alarm was
received. 1-GW-PCV-117 does NOT receive a close signal.
C. 1-GW-FCV-101 closed when 1-GW-RI-178-1 HI radiation alarm was received.
1-GW-PCV-117 does NOT receive a close signal.
D. 1-GW-FCV-101 AND 1-GW-PCV-117 remained open untiI1-GW-RI-178-2 HI
radiation alarm was received.
42
North Anna Power Station
2008 SRO Exam
43.
Given the following:
A LOCA occurred on Unit 1 thirty minutes ago.
The crew is performing 1-E-1, Loss of Reactor or Secondary Coolant.
1-RM-RMS-165 and 1-RM-RMS-166, Containment High Range Radiation
Monitors, both have amber and red lights illuminated in the control room.
Which ONE of the following describes the additional indications observed if an actual
high radiation condition exists?
A. SAFE/RESET green light on drawers LIT;
UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 2.
B. SAFE/RESET green light on drawers LIT;
UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 1.
C. SAFE/RESET green light on drawers NOT LIT;
UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 2.
D. SAFE/RESET green light on drawers NOT LIT;
UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 1.
43
North Anna Power Station
2008 SRO Exam
44.
Which ONE of the following states the power supplies to AFW Discharge MOVs,
1-FW-MOV-100A, B, C?
B. 1A Semi-Vital Bus
C. 1B Semi-Vital Bus
D. MCC1H1-2N
44
45.
North Anna Power Station
2008 SRO Exam
In accordance with the applicable Fire Contingency Action (FCA) procedure, which
ONE of the following describes actions required to maintain power supply to the Unit-1
remote monitoring excore neutron flux detector (channel one) following a fire in the
given location?
A. Following a fire in the Main Control Room, supplied from Unit-2 vital bus inverter
2-1, which will be disconnected from vital bus 2-1.
B. Following a fire in Unit-1 emergency switchgear, supplied from Unit-2 vital bus
inverter 2-1, which will be disconnected from vital bus 2-1.
C. Following a fire in the Main Control Room, supplied from Unit-1 vital bus inverter
1-1, which will be disconnected from vital bus 1-1.
D. Following a fire in Unit-1 emergency switchgear, supplied from Unit-1 vital bus
inverter 1-1, which will be disconnected from vital bus 1-1.
45
North Anna Power Station
2008 SRO Exam
46.
Given the following:
Both Units are at 100 % power.
A Fire in RSST 'A' causes an overcurrent lockout on Transfer Bus D.
Which ONE of the following describes the battery chargers that are temporarily
deenergized?
A.
1-111 and 1-IV
B. 2-1 and 2-11
c. 2-111 and 2-IV
D.1-land1-11
46
47.
North Anna Power Station
2008 SRO Exam
If a loss of Battery Charger 1-1 were to occur, what would be the effect on the operation
of its associated inverter and the vital DC bus?
A. NO static switch automatic transfer; vital DC bus voltage initially decreases by
several volts and then continues to decrease at the same rate over time.
B. Static switch automatic transfer occurs; vital DC bus voltage initially decreases by
several volts and then continues to decrease at a faster rate over time.
C. Static switch automatic transfer occurs; vital DC bus voltage initially decreases by
several volts and then continues to decrease at the same rate over time.
D. NO static switch automatic transfer; vital DC bus voltage initially decreases by
several volts and then continues to decrease at a faster rate over time.
47
North Anna Power Station
2008 SRO Exam
48.
Given the following:
A lightning strike has occurred resulting in a loss of the North Anna Switchyard.
The 1J EDG Battery and Battery Charger are BOTH lost.
125 VDC Bus 1-1 is lost.
A spurious SI occurs.
The crew has entered 1-E-O, Reactor Trip or Safety Injection, and manually
actuated SI.
Which ONE of the following describes the reason that no J Train ESF equipment is
running?
A.
1J EDG did NOT start due to loss of the DC fuel oil pump.
B. 1J EDG started, but the EDG output breaker did NOT close due to loss of DC field
flash capability.
C. 1J EDG started and the EDG output breaker is closed, but no control power is
available to 1J Bus load breakers.
D. 1J EDG did NOT start due to loss of power to both start circuits.
48
North Anna Power Station
2008 SRO Exam
49.
Unit 1 is operating at 100% power.
The following alarm is received:
1F-F8, SAND FLTR IA SUPPLY LO PRESS.
The OATC notes instrument air pressure is 85 psig and rapidly decreasing.
The crew initiates 1-AP-28, LOSS OF INSTRUMENT AIR.
Instrument Air pressure continues to lower.
The SRO directs tripping the reactor and closing Main Steam Trip Valves.
Which ONE of the following identifies the reason for manually closing the Main Steam
Trip Valves?
A. To avoid a High Steam Line Delta P safety injection due to closure of a single main
steam trip valve.
B. To avoid a High Steam Flow safety injection due to closure of a single main steam
trip valve.
C. To avoid a Lo-Lo SG level reactor trip due to closure of all main steam trip valves.
D. To avoid a High PZR Pressure reactor trip due to closure of all main steam trip
valves.
49
North Anna Power Station
2008 SRO Exam
50.
Given the following:
The crew is preparing to release WGDT 1B.
The maximum allowed flowrate per the release permit is 300 SCFM.
Which ONE of the following describes the preferred method for controlling the WGDT
release flow rate in accordance with 0-OP-23.2, WGDT and Waste Gas Diaphragm
Compressors?
A.
1-GW-FCV-101, WGDT to Process Vent, should be placed in AUTOMATIC and
adjusted to control flow rate at less than 3 SCFM.
B. 1-GW-FCV-1 01, WGDT to Process Vent, should be placed in MANUAL and'
adjusted to control flow rate at less than 3 SCFM.
C. 1-GW-FCV-101, WGDT to Process Vent, should be placed in AUTOMATIC and
adjusted to control flow rate at 290 i: 5 SCFM.
D. 1-GW-FCV-1 01, WGDT to Process Vent, should be placed in MANUAL and
adjusted to control flow rate at 290 i: 5 SCFM.
50
North Anna Power Station
2008 SRO Exam
51.
Given the following:
Each Unit has a containment vacuum pump running.
1-GW-RI-178-3, Process Vent particulate radiation Monitor indication spiked,
causing an ALERT and HIGH alarm to lock in.
Which ONE of the following describes the plant response?
A. ONLY the unit 1 vacuum pump discharge valve will automatically close.
B. ONLY the unit 1 vacuum pump will trip.
C. Both units' vacuum pumps will trip; discharge valves remain open.
D. Both units' vacuum pump discharge valves will automatically close.
51
52.
North Anna Power Station
2008 SRO Exam
Initial Conditions:
Operations noted a step increase on 1-CH-RM-128, Unit 1 Reactor Coolant
Letdown Monitor.
Health Physics identified a hot spot in the letdown piping four (4) feet from
1-CH-RM-128 detector.
General area survey taken at 1-CH-RM-128 detector was 60 mRem/hour prior to
flushing the hot spot.
No Radiation Monitors in alarm.
Current Conditions:
Operations flushed the hot spot and relocated it to two (2) feet from
1-CH-RM-128 detector.
1-CH-RM-128 Hi alarm -LIT.
Annunciator 1K-D2, Rad Monitor System Hi Rad Level- LIT solid.
Based on current conditions, which ONE of the following identifies the expected
general area survey at 1-CH-RM-128 detector, and also predicts the response of
Annunciator 1K-D2, if a high alarm subsequently occurs on 1-SV-RM-121, Condenser
Air Ejector Radiation Monitor?
A. 120 mRem/hour;
Annunciator 1K-D2 will remain LIT solid.
B. 240 mRem/hour;
Annunciator 1K-D2 will remain LIT solid.
C. 120 mRem/hour;
Annunciator 1K-D2 will blink and horn will sound until acknowledged.
D. 240 mRem/hour;
Annunciator 1K-D2 will blink and horn will sound until acknowledged.
52
North Anna Power Station
2008 SRO Exam
53.
Given the following:
Unit 1 is at 100% power.
Three BC fans are running in SLOW speed and the fourth is in standby.
Computer alarms are received on several components cooled by the Bearing
Cooling System.
Subsequently, the following alarms are received 90 seconds apart:
1A-F4, BASIN TEMP HI/LOW
1T-C1, HYDROGEN TEMP OR CORE MONITOR
The crew enters 1-AP-19, Loss of Bearing Cooling Water, and verifies a Bearing
Cooling Pump is running.
Which ONE of the following describes the initial action required in accordance with
1-AP-19?
A. Bypass 1-BC-TCV-104, Generator Hydrogen Cooler TCV, to lower hydrogen
temperature.
B. Place Bearing Cooling in Lake - to - Lake Mode and verify the operation of the Circ
Water System to ensure cooling requirements are met.
C. Start available Bearing Cooling Tower Fans or shift fans to high speed; verify
Bearing Cooling temperatures are decreasing.
D. Verify Generator Hydrogen temperature is above the alarm setpoint and initiate a
plant load reduction until the alarm is clear.
53
North Anna Power Station
2008 SRO Exam
54.
Given the following:
Unit 1 is at 40°A> power.
The B SG has developed a 60 gpd tube leak.
Operators are preparing to shutdown the Unit due to fuel failure resulting in ReS
activity increasing at a steady rate.
Based on these plant conditions, which ONE of the following identifies how
1-SV-RM-121, Condenser Air Ejector Radiation Monitor, and 1-MS-RI-191,
"B" SG N-16 Radiation Monitor, will respond as RCS activity increases?
A.
1-SV-RM-121 indication will not change;
1-MS-RI-191 indication will not change.
B. 1-SV-RM-121 indication will not change;
1-MS-RI-191 indication will increase.
C. 1-SV-RM-121 indication will increase;
1-MS-RI-191 indication will not change.
D. 1-SV-RM-121 indication will increase;
1-MS-RI-191 indication will increase.
54
North Anna Power Station
2008 SRO Exam
55.
Given the following:
Both units are at 100% power.
Due to voltage and frequency fluctuations on the grid, the crew is performing
actions contained in 0-AP-8, Response to Grid Instability.
The crew has verified equipment operability.
Which ONE of the following describes the operation of the Main Generator Voltage
Regulators per 0-AP-8, and the condition that requires the offsite power source to be
declared inoperable?
A. Place voltage regulators in MANUAL; grid voltage decreases to 504 kV
B. Maintain voltage regulators in AUTO; grid voltage increases to 536 kV
c. Place voltage regulators in MANUAL; grid voltage increases to 536 kV
D. Maintain voltage regulators in AUTO; grid voltage decreases to 504 kV
55
North Anna Power Station
2008 SRO Exam
56.
Which ONE (1) of the following describes the operation of Instrument Air Compressor
"1-IA-C-1" when it is placed in AUTO?
A. Compressor will start and run continuously for an indefinite period of time.
Unloader valves will CLOSE when pressure drops to 103 psig. Unloader valves will
OPEN when pressure rises to 109 psig.
B. Compressor will start and run continuously for an indefinite period of time.
Unloader valves will CLOSE when pressure drops to 98 psig. Unloader valves will
OPEN when pressure rises to 106 psig.
C. Compressor will start and load when pressure drops to 98 psig. Compressor will
unload when pressure rises to 106 psig.
D. Compressor will start and load when pressure drops to 103 psig. Compressor will
unload and shut down when pressure increases to 109 psig.
56
North Anna Power Station
2008 SRO Exam
57.
Instrument Air Compressor 1-IA-C-1 has been running loaded for the past 15 minutes.
Which ONE of the following choices completes the following sentence?
Either a
OR a
will result in a trip of the Air Compressor.
A. Low Oil Pressure;
Cooling System Fault caused by low cooling system DP
B. High Discharge Pressure;
Cooling System Fault caused by high pressure on surge line
.
C. High Discharge Pressure;
Cooling System Fault caused by low cooling system DP
D. Low Oil Pressure;
Cooling System Fault caused by high pressure on surge line
57
North Anna Power Station
2008 SRO Exam
58.
Given the following:
A loss of Instrument Air is occurring on Unit 1.
The immediate actions of 1-AP-28, Loss of Instrument Air, are complete.
Instrument Air pressure is 90 psig and dropping slowly.
Which ONE of the following describes the compressor status and the action to be
taken based on the system pressure in accordance with 1-AP-28?
A. All Service Air Compressors running and loaded; all Instrument Air Compressors
running unloaded;
Isolate Instrument Air to Containment by closing 1-IA-TV-102A or 1-IA-TV-102B,
Containment Instrument Air Trip Valves.
B. All Service Air Compressors running and loaded; all Instrument Air Compressors
running unloaded;
Verify Instrument Air supplied to Containment by verifying open 1-IA-TV-1 02A and
1-IA-TV-102B, Containment Instrument Air Trip Valves.
C. All Instrument and Service Air Compressors running and loaded;
Isolate Instrument Air to Containment by closing 1-IA-TV-102A or 1-IA-TV-102B,
Containment Instrument Air Trip Valves.
D. All Instrument and Service Air Compressors running and loaded;
Verify Instrument Air supplied to Containment by verifying open 1-IA-TV-1 02A and
1-IA-TV-102B, Containment Instrument Air Trip Valves.
58
North Anna Power Station
2008 SRO Exam
59.
Given the following:
A LOCA has occurred on Unit 1.
The following conditions exist:
RCS pressure is 1700 psig.
Containment pressure has peaked at 21 psia and is now slowly decreasing.
The crew is performing 1-E-0, Reactor Trip or Safety Injection.
The RO is performing Attachment 5, Verification of Phase A Isolation.
The following valves are identified as OPEN:
1-CH-MOV-1115B, RWST To Charging Pumps Isolation
1-CH-MOV-1289B, Normal Charging Line Isolation
1-IA-TV-102A, Containment Instrument Air Trip Valve
1-SW-MOV-108A, Service Water to CC Heat Exchanger Isolation
For the current plant conditions, which ONE of the following valves must be
repositioned to place it in the required accident configuration?
A. 1-SW-MOV-108A
B. 1-CH-MOV-1115B
C. 1-IA-TV-102A
D. 1-CH-MOV-1289B
59
North Anna Power Station
2008 SRO Exam
60.
Given the following:
A LOCA has occurred on Unit 1.
The crew is performing 1-ES-1.2, Post LOCA Cooldown and Depressurization.
During the SI flow reduction sequence, the following conditions exist:
All RCPs are stopped.
Two Charging Pumps are running.
RCS pressure is 1100 psig and stable.
RCS Subcooling based on Core Exit TCs is 55°F
Pressurizer level is 44%.
Containment pressure is 20.9 psia.
Which ONE of the following describes the response to these conditions in accordance
with 1-ES-1.2, and the reason for this response?
A. Continue the RCS cooldown while stopping one Charging Pump;
RCS subcooling is adequate to prevent loss of subcooling margin when one
Charging Pump is stopped.
B. One Charging Pump may be stopped ONLY IF at least one Low Head SI pump is
running;
RCS subcooling is NOT adequate to prevent loss of subcooling margin when one
Charging Pump is stopped.
C. Maintain PZR level stable or increasing while stopping one Charging Pump;
RCS subcooling is adequate to prevent loss of subcooling margin when one
Charging Pump is stopped.
D. Charging Pumps must remain running with flow aligned to the BIT;
RCS subcooling is NOT adequate to prevent loss of subcooling margin when one
Charging Pump is stopped.
60
61.
North Anna Power Station
2008 SRO Exam
Initial Conditions:
Unit 1 tripped from 100°1'<> power due to a loss of all feed flow.
Multiple failures caused a loss of all AFW.
Current conditions:
ALL SG Wide Range levels are 12°1'<> and slowly lowering.
RCS Hot Leg Temperatures are 5600F and slowly lowering.
Core Exit TCs are 5650F and slowly lowering.
Local actions have restored the capability to feed from AFW.
Which ONE of the following describes the method for recovery of Heat Sink in
accordance with 1-FR-H.1, Loss of Secondary Heat Sink, and includes the Basis for
that method?
A. Feed only ONE SG at 100 gpm;
Minimum flow to ensure adequate heat sink.
B. Feed all three SGs at 340 gpm total flow;
Minimum flow to ensure adequate heat sink.
C. Feed all three SGs at 340 gpm total flow;
Ensure symetric cooling during Natural Circulation.
D. Feed only ONE SG at 100 gpm;
Limit thermal stresses to SG components.
61
North Anna Power Station
2008 SRO Exam
62.
Given the following:
A loss of off-site power due to a Tornado hitting the switchyard.
The crew has stabilized the Unit using 1-ES-O.1, Reactor Trip Response.
Operations Management has directed performance of a Natural Circulation
Cooldown.
Which ONE of the following procedures will be used to perform the RCS Cooldown,
and which ONE of the following is the MAXIMUM cooldown rate allowable in
accordance with the EOP that will be used?
A. ES-O.2A, Natural Circulation Cooldown with CRDM Fans; 15 degrees F/Hr.
B. ES-O.2B, Natural Circulation Cooldown without CRDM Fans; 25 degrees F/Hr.
C. ES-O.2B, Natural Circulation Cooldown without CRDM Fans; 15 degrees F/Hr.
D. ES-O.2A, Natural Circulation Cooldown with CRDM Fans; 25 degrees F/Hr.
62
North Anna Power Station
2008 SRO Exam
63.
Upon entry into 1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators, the
crew determines that RCS cooldown rate is 10goF/Hr.
Which ONE (1) of the following identifies the requirement for controlling AFW flow in
accordance with 1-ECA-2.1?
A. Total flow is maintained >340 gpm until ANY SG narrow range level is >110/0.
B. Total flow is maintained >340 gpm until ALL 8G narrow range levels are >11%
C. Flow is reduced to 100 gpm to each 8G, and narrow range level in ALL 8G's is
controlled at less than 50%.
D. Flow is reduced to 100 gpm to each SG, and narrow range level in ALL 8G's is
controlled at greater than 11%.
63
North Anna Power Station
2008 SRO Exam
64.
Given the following:
A small-break LOCA occurred on Unit 1.
The crew transitions to 1-E-1, Loss of Reactor or Secondary Coolant.
Which ONE of the following will FIRST cause an ORANGE condition on the
Containment CSF Status Tree?
A. Recirc Spray sump level at 4 feet 10 inches.
B. Annunciator 1J-A6, RX CONT SUMP HI LEVEL, is LIT.
C. Containment circular sump level indication off-scale high.
D. Recirc Spray sump level at 11 feet 10 inches.
64
North Anna Power Station
2008 SRO Exam
65.
A Small Break LOCA has occurred on Unit 1.
The following plant conditions exist:
Complications in recovery have resulted in some core damage.
Containment Pressure peaked at 22 psia and is slowly decreasing.
The team has transitioned to 1-FR-Z.3, Response to High Containment
Radiation Level.
Which ONE of the following describes a strategy provided by 1-FR-Z.3 to mitigate the
condition?
A. Place Containment Atmosphere Filtration System in service.
B. Start Outside Recirc Spray pumps and injecting the CAT.
C. Start Inside Recirc Spray pumps and injecting the CAT.
D. Vent Containment via the Iodine Filter banks.
65
North Anna Power Station
2008 SRO Exam
66.
In Emergency Operating Procedure 1-E-O, Reactor Trip or Safety Injection, steps
designated with an asterisk (*) next to the step are
_
these steps apply from the time they are encountered until
_
A. Continuous Action Steps;
transition from 1-E-O is made
B. Decision Making Steps;
the EOP Network is exited
C. Decision Making Steps;
transition from 1-E-O is made
D. Continuous Action Steps;
the EOP Network is exited
66
67.
North Anna Power Station
2008 SRO Exam
In accordance with OP-AP-300, Reactivity Management, reactor power is required to
be reduced below 100°A> PRIOR to performing which ONE of the following evolutions?
A. Reducing Steam Generator Blowdown Flow Rate
B. Performing a blended makeup to the RCS
C. Operating the Steam Driven Aux Feed Pump Turbine
D. Raising Letdown temperature
67
North Anna Power Station
2008 SRO Exam
68. Given the following:
Unit 1 is shut down in preparation for Refueling in accordance with 1-0P-4.1,
Controlling procedure for Refueling.
In accordance with 1-0P-4.1, which ONE of the following choices describes
(1) the method of filling the Refueling Cavity
and
(2) which evolution constitutes the FIRST Core Alteration?
A. (1) Gravity fill from RWST, then LHSI pump
(2) Lifting of the Reactor Vessel Upper Internals
B. (1) LHSI pump ONLY
(2) Lifting of the Reactor Vessel Upper Internals
C. (1) LHSI pump ONLY
(2) Control Rod Drive Shaft unlatching
D. (1) Gravity fill from RWST, then LHSI pump
(2) Control Rod Drive Shaft unlatching
68
North Anna Power Station
2008 SRO Exam
69.
Given the following:
An approach to criticality is in progress in accordance with 1-0P-1.5, Unit
Startup from Mode 3 to Mode 2.
Source Range count rate prior to the last rod withdrawal was 4,000 CPS.
Source Range count rate is now 7,000 CPS and slowly increasing.
Source Range startup rate is +0.3 OPM and stable.
Two minutes have elapsed since the last rod withdrawal.
Control Bank 'C' is at 110 steps.
Which ONE of the following describe the sequence of actions required by 1-0P-1.5?
A.
Initiate Boration at greater than or equal to 10 gpm, then trip the reactor.
B. Allow Source Range count rate to stabilize, then continue rod withdrawal.
C. Insert Control Bank '0' to 5 steps, then trip the reactor.
O. Initiate Boration at greater than or equal to 10 gpm, then insert Control Bank '0' to 5
steps.
69
North Anna Power Station
2008 SRO Exam
70.
Given the following:
Unit 1 is at 45% power.
Plant startup is in progress.
No other evolutions are in progress
Which ONE of the following parameter values requires Technical Specification action
within ONE (1) hour?
A. Containment air partial pressure 12.9 psia.
B. Quadrant Power Tilt Ratio 1.022.
C. RCS unidentified leakage is 1.20 gpm.
D. RWST temperature 38 degrees F.
70
North Anna Power Station
2008 SRO Exam
71.
Which ONE of the following Periodic Tests is designated as an Infrequently Conducted
or Complex Evolution?
A. Rod operability testing in accordance with 1-PT-17.1, Control Rod Operability.
B. Turbine overspeed trip test in accordance with 1-PT-34.5, Turbine-Generator
Overspeed Trip Test.
C. Turbine valve freedom test in accordance with 1-PT-34.3, Turbine Valve Freedom
Test.
D. Solid State Protection System testing in accordance with 1-PT-36.1A, Train A
Reactor Protection and ESF Logic Actuation Test.
71
North Anna Power Station
2008 SRO Exam
72.
Given the following:
Unit 1 is defueled and the fuel assembly insert shuffle is in progress.
Annunciator 1K-D3, RAD MONITOR SYSTEM FAILURE TEST, actuates.
The new fuel storage area radiation monitor is noted to be pegged high and
unresponsive to source check.
The fuel pit bridge radiation monitor indication has not changed.
Health Physics reports radiation levels in the fuel building have not changed.
Which ONE of the following describes the FIRST action that will be required in
accordance with O-AP-5.1, Common Unit Radiation Monitoring System?
A. Verify the fuel building ventilation exhaust is aligned to the charcoal filter.
B. Reset the new fuel storage area radiation monitor by pulling and reinserting fuses.
C. Place the fuel building radiation automatic interlock key switch in DISABLE within
two minutes.
D. Place the fuel building radiation automatic interlock key switch in ENABLE within
two minutes.
72
North Anna Power Station
2008 SRO Exam
73.
Which ONE of the following identifies the 10 CFR 20 annual limit for TEDE and also
identifies the EPIP 4.04 Emergency Exposure Limit for saving valuable equipment?
A. 5 rem;
25 rem
B. 3 rem;
10 rem
C. 5 rem;
10 rem
D. 3 rem;
25 rem
73
North Anna Power Station
2008 SRO Exam
74.
Given the following:
Both Units are at 1DD°A> power.
The following alarm is received on Unit 2 Panel F:
UNIT #1 ANN SYS POWER SUPPLY FAILURE
The crew enters 1-AP-6, Loss of Main Control Room Annunciators.
Which ONE of the following describes requirements in accordance with 1-AP-6 if the
Unit 1 Annunciators are not immediately restored?
A. NOT required to station an additional operator to monitor the unit-1 PCS;
Log AFD every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
B. Station an additional operator to monitor the unit-1 PCS;
Log AFD every hour.
C. NOT required to station an additional operator to monitor the unit-1 PCS;
Log AFD every hour.
D. Station an additional operator to monitor the unit-1 PCS;
Log AFD every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
74
North Anna Power Station
2008 SRO Exam
75.
Given the following:
Unit 1 is in Mode 5.
RCS Drain Down to Mid Loop is in progress in preparation for welding on a Hot
Leg opening.
RHR Pump 1A is in service.
RHR Pump 1B is available.
During the drain down, RHR amps and discharge pressure begin fluctuating
erratically.
RCS temperature has risen from 121 degrees F to 127 degrees F.
The crew enters 1-AP-11, Loss of RHR, and stops the RCS drain down.
Which ONE (1) of the following describes the next actions that will be required in
accordance with 1-AP-11?
A. Reduce RHR flow to minimum required to maintain RCS temperature and/or raise
RCS level to ensure at least 10 inches above the Hot Leg centerline.
B. Reduce RHR flow to minimum required to maintain RCS temperature and maximize
CC flow to inservice RHR heat exchangers.
C. Stop RHR Pump 1A and initiate Attachment 8, Reflux Boiling to control RCS
temperature.
D. Stop RHR Pump 1A and immediately start RHR Pump 1B, then verify that RCS
temperature stabilizes.
75
76.
North Anna Power Station
2008 SRO Exam
Initial conditions:
A spurious Turbine Runback occurred on Unit 1.
Tave was 5.5 degrees F higher than Tref and rising.
Control Bank D rods were inserting at the required rate.
Current conditions:
Reactor power 580/0.
Steam Dumps closed.
Rod Motion stopped.
Tave and Tref are approximately equal and stable.
Control Bank D Group Step counters are at 170 steps.
All Control Bank D rods indicate approximately 170 steps, with the exception of
Rod H-8, which is at 184 steps.
A blown fuse is the cause of the mispositioned rod.
Which ONE of the following idenifies (1) the rod speed of rod H-8 PRIOR to the blown
fuse and (2) whether or not the H-8 control rod is operable?
B. 64 SPM ; H-8 is INOPERABLE.
C. 72 SPM ; H-8 is INOPERABLE.
76
North Anna Power Station
2008 SRO Exam
77.
Given the following:
Unit 1 is in Mode 6 with refueling cavity level at 289' 10".
Upper internals have been removed.
1A RHR pump is in operation with 1B RHR pump in standby.
An electrical fault on 1H bus causes a loss of the bus.
Which ONE of the following describes the action required, and the basis for the action
in accordance with Technical Specifications?
A. Immediately initiate action to establish >/= 23 feet of water above the top of the
reactor vessel flange;
provides acceptable results in conjunction with actions to initiate containment
closure to limit radioactive release to the environment.
B. Immediately suspend any RCS makeup from sources with a boron concentration
less than that required by TS 3.9.1;
ensures that there will be NO RCS makeup without adequate mixing.
C. Immediately initiate action to establish >/= 23 feet of water above the top of the
reactor vessel flange;
ability to remove decay heat and ensure mixing of borated RCS water is degraded.
D. Immediately suspend any RCS makeup from sources with a boron concentration
less than that required by TS 3.9.1;
ensures that if RCS boron concentration is reduced due to RCS makeup,
acceptable margin for subcritical operation is maintained.
77
North Anna Power Station
2008 SRO Exam
78.
Given the following:
Unit 1 has been at 100% power for 12 months.
The following alarms are received approximately 5 minutes apart:
1J-D7, ACCUM 1A-1B-1C HI-LO LEVEL
1J-D8, ACCUM 1A-1B-1C HI-LO PRESS
SI Accumulator levels and pressures are as follows:
1A
18
1C
Level
67%
72°Al
590/0
Pressure
655 psig
670 psig
610 psig
Given these levels and pressures which ONE of the following predicts the reason for
the alarms AND identifies the status of accumulator operability in accordance with
Technical Specifications?
A. Check valve leakage is occurring;
SI accumulators are all operable.
B. Vent valve leakage is occurring;
one SI accumulator is inoperable.
C. Vent valve leakage is occurring;
SI accumulators are all operable.
D. Check valve leakage is occurring;
one SI accumulator is inoperable.
78
North Anna Power Station
2008 SRO Exam
79.
The following conditions exist:
Unit 1 is at 100% power.
1-SI-P-1B, "B" Low Head Safety Injection Pump is tagged out for maintenance.
The 1H Emergency Diesel Generator (EDG) is subsequently determined to be
inoperable due to the discovery that non-qualified parts were used the last time
maintenance was performed on the EDG.
Based on these plant conditions, which ONE of the following identifies the equipment
that must be declared inoperable AND the required action in accordance with
Technical Specifications?
A. Declare the 1H EDG and 1-SI-P-1A, "A" Low Head Safety Injection Pump
Verify correct breaker alignment and indicated power availability for each required
offsite circuit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
B. Declare the 1H EDG inoperable; 1-SI-P-1A, "A" Low Head Safety Injection Pump
remains operable;
Verify correct breaker alignment and indicated power availability for each required
offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
c. Declare the 1H EDG and 1-SI-P-1A, "A" Low Head Safety Injection Pump
Verify correct breaker alignment and indicated power availability for each required
offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
D. Declare ONLY the 1H EDG inoperable; 1-SI-P-1A, "A" Low Head Safety Injection
Pump remains operable;
Verify correct breaker alignment and indicated power availability for each required
offsite circuit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
79
North Anna Power Station
2008 SRO Exam
80.
Given the following:
Both Units were initially at 100DA> power with 1J EDG OOS.
Operators began Unit 1 shutdown due to a steam leak inside Containment on the
BSG.
1-RC-PT-1444 failed high causing the associated PORV, 1-RC-PCV-1455C to
open.
Attempts to close PORV 1-RC-PCV-1455C and the associated PORV Block
Valve, 1-RC-MOV-1536 were unsuccessful and operators tripped the Unit.
The following occurred immediately following the reactor trip:
B SG failed catastrophically inside Containment
Off-site power was lost
Low Head SI pump 1-SI-P-1A tripped on overcurrent during startup.
Power Supply estimates off-site power restoration in 1.5 to 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 describes the procedure the operators will transition to
when leaving 1-E-0, Reactor Trip or Safety Injection, AND how power is required to be
restored to 1J Emergency Bus?
A.
1-E-1, Loss of Reactor or Secondary Coolant;
restore power to 1J Emergency Bus when off-site power becomes available.
B. 1-E-1, Loss of Reactor or Secondary Coolant;
restore power to 1J Emergency Bus using the SBO diesel.
C. 1-E-2, Faulted Steam Generator Isolation;
restore power to 1J Emergency Bus when off-site power becomes available.
D. 1-E-2, Faulted Steam Generator Isolation;
restore power to 1J Emergency Bus using the SBO diesel.
80
North Anna Power Station
2008 SRO Exam
81.
Unit 1 is at 100% power.
1K-G1, SFGDS PROT SYS TR A TROUBLE has been alarming intermittently.
Instrument Department has determined a 48VDC power supply in Train A is degrading
and will most likely fail completely in the near future.
Which ONE of the following describes the correct response?
Reference Provided
A. Online replacement of the power supply is permitted;
following power supply replacement the Reactor Trip Bypass Breaker may be
closed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform 1-PT-36.1A, Train A Reactor Protection and
ESF Logic Actuation Logic Test.
B. Online replacement of the power supply is NOT permitted;
be in Hot Standby within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C. Online replacement of the power supply is NOT permitted;
be in Hot Standby within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
D. Online replacement of the power supply is permitted;
following power supply replacement the Reactor Trip Bypass Breaker may be
closed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to perform 1-PT-36.1A, Train A Reactor Protection and
ESF Logic Actuation Logic Test.
81
North Anna Power Station
2008 SRO Exam
82.
Given the following:
A LOCA is in progress on Unit 1.
All RCPs are stopped.
RVLIS Full Range is 27°~.
Core Exit TCs are reading 1250 degrees F.
ALL SG NR levels are OFF-SCALE low.
NO source of SG feed has been established.
NO source of ECCS has been established.
The crew has attempted secondary depressurization in accordance with FR-C.1,
Response to Inadequate Core Cooling, but the attempt was ineffective.
Given these plant conditions, which ONE of the following identifies the procedure
action to mitigate this event?
A. Immediately transition to SACRG-1, Severe Accident Control Room Guideline Initial
Response, BEFORE opening PZR PORVs and Block Valves, and other RCS Vent
Paths.
B. Remain in FR-C.1, open PZR PORVs and Block Valves, and other RCS Vent
Paths.
C. Open PZR PORVs and Block Valves, and other RCS Vent Paths and THEN
transition to SACRG-1, Severe Accident Control Room Guideline Initial Response.
D. Remain in FR-C.1, start one RCP in an idle loop.
82
North Anna Power Station
2008 SRO Exam
83.
Given the following:
Unit 1 is in Mode 5 with RCS draindown in progress.
The crew observes 1B RHR Pump discharge flow and motor amps
oscillating.
The crew isolates known RCS drain paths and maximizes Charging flow.
RCS level continues to decrease.
Annunciator E-A8, RHR SYSTEM La FLOW, is alarming intermittently.
Containment sump pumps are running continuously.
An operator leaving Containment reports leakage observed from the PZR Surge
Line.
Which ONE of the following describes the procedural guidance that will mitigate these
plant conditions?
A. Perform 1-AP-17, Shutdown LOCA; initiate Attachment 8, Hot Leg Injection.
B. Perform 1-AP-11, Loss of RHR, Attachment 2, Minimum RCS Level for Indicated
Flow.
C. Perform 1-AP-17, Shutdown LOCA, Attachment 7, Cold Leg Injection.
D. Perform 1-AP-11, Loss of RHR, Attachment 3, Determining Acceptable RHR Flow
Reductions.
83
84.
North Anna Power Station
2008 SRO Exam
Unit 1 is at 1000/0 power. Unit 2 is in Mode 5.
Unit 1 and 2 CC systems are split.
The OATC reports the following alarms and indications:
1G-E8, CaMP COOL PP 1B AUTO TRIP
1G-B3, CC HX 1A-1B CC OUTLET La FLOW
1C-C4, RCP 1A-B-C CC THERM BARR HI/La FLOW
1A-E6, RCP 1B VIBRATION ALERT/DANGER
RCP Thermal Barrier Heat Exchanger flow indicators all read 0 GPM.
RCP Motor Bearing temperatures are 146°F and rising at 5°F per minute.
1B RCP Vibration readings:
2-3 mils Seismic
8-10 mils Proximity
Given these plant conditions, which ONE of the following identifies the required
procedure AND also identifies the Design Basis of the CC System in accordance with
the Technical Specification Bases?
A. 1-AP-15, Loss of Component Cooling;
TWO CC Subsystems are sufficient to accomplish a fast cooldown of one unit while
maintaining normal loads on the other unit.
B. 1-E-0, Reactor Trip or Safety Injection;
THREE CC Subsystems are sufficient to accomplish a fast cooldown of one unit
while maintaining normal loads on the other unit.
C. 1-AP-15, Loss of Component Cooling;
THREE CC Subsystems are sufficient to accomplish a fast cooldown of one unit
while maintaining normal loads on the other unit.
D. 1-E-0, Reactor Trip or Safety Injection;
TWO CC Subsystems are sufficient to accomplish a fast cooldown of one unit while
maintaining normal loads on the other unit.
84
North Anna Power Station
2008 SRO Exam
85.
Given the following:
Unit 1 is in Mode 3 during a plant cooldown.
Chemistry sample of the Quench Spray System Chemical Addition Tank
determines that NaOH concentration is 10%
by weight.
Chemical Addition Tank contains approximately 5510 gallons.
1-QS-P-1 B, Quench Spray Pump 1B, is out of service.
Which ONE of the following describes how the current status of the Quench
Spray/Chemical Addition Tank affects the plant during a Design Basis LOCA in
accordance with the Technical Specification Bases?
A. Chemical Addition Tank NaOH concentration (10% by weight) is outside of limits
which affects the pH of the resultant Containment sump water solution and the
ability to effectively remove Iodine following a DBA LOCA.
B. Chemical Addition Tank volume (5510 gallons) is outside of limits which affects the
ability to maintain Containment within design pressure limits and affects the ability
to maintain Iodine at acceptable levels following a DBA LOCA.
C. Inoperability of 1-QS-P-1 B will result in a Containment peak temperature higher
than the value calculated in the accident analysis for a DBA LOCA.
D. Inoperability of 1-QS-P-1 B will result in a Containment peak pressure higher than
the value calculated in the accident analysis for a DBA LOCA.
85
North Anna Power Station
2008 SRO Exam
86.
Given the following:
Unit 1 core off-load in progress.
The 3 most recently off-loaded irradiated fuel assemblies are stored as follows:
Assembly(Enrichment)
Assembly A (4.6%)
Assembly B (3.20/0)
Assembly C (3.2%)
Burnup
30,000 MWD/MTU
30,000 MWD/MTU
20,000 MWD/MTU
Location
Non-Matrix location
Low-Reactivity 5X5 matrix
Low Reactivity 5X5 matrix
Which ONE of the following identifies the minimum required action in accordance with
Technical Specification 3.7.18, Spent Fuel Pool Storage AND the Bases for the action?
Reference Provided
A. ONLY ONE fuel assembly is required to be moved;
ensures that Keff will remain <0.95 for all postulated accidents assuming that the
soluble boron in the Spent Fuel Pool is at the TS 3.7.17, Fuel Storage Pool Boron
Concentration, minimum limit.
B. TWO fuel assemblies are required to be moved;
ensures that Keff will remain <0.95 for all postulated accidents assuming that the
soluble boron in the Spent Fuel Pool is at the TS 3.7.17, Fuel Storage Pool Boron
Concentration, minimum limit.
C. TWO fuel assembly are required to be moved;
ensures that Keff will remain <0.95 for all postulated accidents assuming NO
soluble boron in the Spent Fuel Pool.
D. ONLY ONE fuel assembly is required to be moved;
ensures that Keff will remain <0.95 for all postulated accidents assuming NO
soluble boron in the Spent Fuel Pool.
86
87.
North Anna Power Station
2008 SRO Exam
Unit 1 has experienced a Steam Generator Tube Rupture.
The crew is performing 1-ES-3.1, Post-SGTR Cooldown Using Backfill.
Core Exit TCs are 345°F
RCS Hot Leg Temperatures are 335°F
RCS Wide Range Pressure is 600 psig
1C RCP is running and the crew has commenced depressurizing the RCS.
Given the above plant conditions, which ONE of the following identifies the parameter
that will determine when the depressurization will be stopped, AND also provides the
Basis for controlling the rate of depressurization?
A. RCP number 1 seal differential pressure;
control the depressurization rate to ensure pressure control is not lost.
B. RCS Subcooling based on Core Exit TCs;
control the depressurization rate to ensure pressure control is not lost.
C. RCS Subcooling based on Core Exit TCs;
control the depressurization rate to minimize head voiding.
D. RCP number 1 seal differential pressure;
control the depressurization rate to minimize head voiding.
87
North Anna Power Station
2008 SRO Exam
88.
Given the following:
Unit 1 is at 100% power.
The following alarm is received:
1B-A5, CW PP 1A-1B-1C-1DAUTO TRIP
CW Pump 1B motor indicates 0 amps
CW Pumps 1A, 1C, and 10 motors indicate 300-310 amps.
Condenser pressure is 3 inches Hg absolute and degrading slowly.
Which ONE of the following describes the mitigation strategy for the event in progress?
A. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; reduce CW Pump
amps to prevent motor damage.
Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration
flow rates during a load reduction is NOT provided in 1-AP-14.
B. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; contact HP to
determine if liquid waste release must be secured.
Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration
flow rates during a load reduction is NOT provided in 1-AP-14.
C. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; contact HP to
determine if liquid waste release must be secured.
Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration
flow rates during a load reduction is provided in 1-AP-14.
D. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; reduce CW Pump
amps to prevent motor damage.
Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration
flow rates during a load reduction is provided in 1-AP-14.
88
North Anna Power Station
2008 SRO Exam
89.
Given the following:
Unit 1 is at 100% power.
120 VAC Vital Bus Inverter 1-11 failed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.
120 VAC Vital Bus 1-11 is being powered from its associated constant voltage
source transformer.
Which ONE of the following identifies the minimum Technical Specification LCOs that
contain required actions for these plant conditions, including the required
compensatory measures in accordance with the Technical Specification Bases?
Reference Provided
A. TS 3.8.7, Inverters - Operating, Limiting Action is required to be entered;
TS 3.8.9, Distribution Systems - Operating, Limiting Action is NOT required to be
entered;
Concurrent planned EDG maintenance is NOT allowed.
B. BOTH TS 3.8.9, Distribution Systems - Operating AND TS 3.8.7, Inverters -
Operating Limiting Actions are required to be entered;
Concurrent planned EDG maintenance is NOT allowed.
C. TS 3.8.9, Distribution Systems - Operating, Limiting Action is required to be
entered;
TS 3.8.7, Inverters - Operating, Limiting Action is NOT required to be entered;
Concurrent planned EDG maintenance can be performed.
D. BOTH TS 3.8.9, Distribution Systems - Operating AND TS 3.8.7, Inverters -
Operating Limiting Actions are required to be entered;
Concurrent planned EDG maintenance can be performed.
89
North Anna Power Station
2008 SRO Exam
90.
Given the following:
1-FR-H.1, Response to Loss of Secondary Heat Sink, is in progress.
Attempts to establish Aux Feedwater flow are unsuccessful.
RCS Bleed and Feed has NOT been initiated.
Main Feedwater flow has just been established and SG levels are as follows:
'1A' 40 % wide range and rising
'1 B' 40% wide range and stable
'1 C' 29 % wide range and lowering
Core exit Tes are stable.
Containment pressure is 19.2 psia.
Which ONE (1) of the following describes the appropriate operator action?
A.
Return to procedure and step in effect and continue efforts to establish AFW flow.
B.
Perform Steps 14 through 23 of 1-FR-H.1 to initiate RCS bleed and feed.
C.
Remain in 1-FR-H.1 until Core Exit TCs indicate a decreasing trend.
D.
Remain in 1-FR-H.1 until all SG wide range levels indicate an increasing trend.
90
North Anna Power Station
2008 SRO Exam
91.
Given the following:
The Unit is in Mode 6.
Rod Unlatching is in progress.
Manipulator Crane radiation monitor, 1-RM-RMS-162, suddenly pegs high.
The following alarms are received:
1K-D2, RAD MONITOR SYSTEM HI RAD LEVEL
1K-D3, RAD MONITOR SYSTEM HI-HI RAD LEVEL
HP has confirmed that radiation levels on the refueling deck are normal and Operations
has declared 1-RM-RMS-162 inoperable.
Which ONE of the following describes the required actions in accordance with 1-AP-5,
Unit 1 Radiation Monitoring System?
A. Verify Control Room Bottled Air dump;
Core alterations may continue with 1-RM-RMS-162 inoperable. Continuous HP
coverage is required.
B. Verify Containment Ventilation Isolation;
Core alterations may NOT continue with 1-RM-RMS-162 inoperable.
C. Verify Control Room Bottled Air dump;
Core alterations may NOT continue with 1-RM-RMS-162 inoperable.
D. Verify Containment Ventilation Isolation;
Core alterations may continue with 1-RM-RMS-162 inoperable. Continuous HP
coverage is required.
91
North Anna Power Station
2008 SRO Exam
92.
Given the following:
Both units are at 100 % power.
1-SW-P-1A and 1-SW-P-1 B are running.
2-SW-P-1 B is OOS.
1-SW-P-1 B trips and 2-SW-P-1A is started.
Which ONE of the following describes the Technical Specification action required, and
the Bases for the action?
A. Restore the Service Water Loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;
Ensures design flows to the RS Heat Exchangers are achieved following a LOCA
with ONE additional failure.
B. Throttle Service Water to CC Heat Exchangers within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;
Ensures design flows to the RS Heat Exchangers are achieved following a LOCA
with -NO additional failures.
C. Restore the Service Water Loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;
Ensures design flows to the RS Heat Exchangers are achieved following a LOCA
with NO additional failures.
D. Throttle Service Water to CC Heat Exchangers within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;
Ensures design flows to the RS Heat Exchangers are achieved following a LOCA
with ONE additional failure.
92
North Anna Power Station
2008 SRO Exam
93.
Given the following:
A reactor trip has occurred on Unit 1.
Following transition to 1-ES-0.1, Reactor Trip Response, the STA reports all
CSF status trees GREEN with the EXCEPTION of Heat Sink, which is YELLOW.
The following SG conditions are observed:
A SG pressure 1050 psig and stable.
A SG level 25%
NR and rising.
B SG pressure 1150 psig and stable.
B SG level 92% NR and rising.
C SG pressure 1050 psig and stable.
C SG level 20%
NR and rising.
B MSIV indicates CLOSED.
AFW flow is 160 GPM to each SG.
The crew determines that entry to a Yellow Path procedure will help mitigate the
event.
Which ONE of the following describes the mitigation strategy used to restore the Heat
Sink Critical Safety Function to GREEN?
A. Perform 1-FR-H.3, Response to Steam Generator High Level; isolate AFW flow to
B SG. Initiate blowdown from B SG and DO NOT dump steam from B SG.
B. Perform 1-FR-H.2, Response to Steam Generator Overpressure; Isolate AFW flow
to B SG and do not restore AFW flow until a steam release path is established.
C. Perform 1-FR-H.2, Response to Steam Generator Overpressure; Verify Main
Feedwater Isolation. Dump steam from B SG to reduce Hot Leg temperatures.
D. Perform 1-FR-H.3, Response to Steam Generator High Level; Verify Main
Feedwater Isolation. Dump steam from B SG to reduce Hot Leg temperatures and
initiate blowdown from B SG.
93
North Anna Power Station
2008 SRO Exam
94.
Given the following:
The date is 6/5/2008.
Both Units are in Mode 1.
Shift complement is at MINIMUM allowed by Technical Specifications.
One of the Reactor Operators becomes ill and must be transported to the
hospital.
TWO potential replacements are identified for call-in.
BOTH replacements have been assigned to OPS Support for the last year.
The last times they were on shift are as follows:
Operator A
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 24 BOP
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on February 23 BOP
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on February 22 BOP
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on January 19 BOP
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on January 18 BOP
Operator B
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 21 RO
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 20 RO
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 19 RO
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 18 RO
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on January 5 WCC
Which ONE of the following identifies the Technical Specification requirement to
replace the Reactor Operator, and which operator will be selected as the replacement?
A. Action must be taken to ensure the Reactor Operator is replaced within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />;
Operator B will be selected.
B. Action must be taken to ensure the Reactor Operator is replaced within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />;
Operator A will be selected.
C. Action must be taken to ensure the Reactor Operator is replaced within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;
Operator B will be selected.
D. Action must be taken to ensure the Reactor Operator is replaced within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;
Operator A will be selected.
94
North Anna Power Station
2008 SRO Exam
95.
Given the following:
The Shift Manager is in the control room discussing an upcoming evolution with
the Unit 2 Unit Supervisor.
The Unit 1 Unit Supervisor is on a plant walkdown when the following events
occur:
Unit 1 experienced a spurious Turbine runback.
While stabilizing the unit at 65%
power, a turbine trip occurred.
The Unit 1 reactor did NOT trip, either automatically or manually from the
control room.
PZR PORV, 1-RC-PCV-1455C, is stuck OPEN.
The associated block valve, 1-RC-MOV-1536, did NOT close when the
OATC took the control switch to close.
Safety Injection is actuated.
The Unit 1 Unit Supervisor was injured while returning to the control room
and needs medical assistance in the Turbine Building.
In accordance with DNAP-0509, Dominion Nuclear Procedure Adherence and Usage,
which ONE of the following identifies who will be the EOP 'Reader,' AND also identifies
the required EOP flowpath upon exiting 1-FR-S.1, Response to Nuclear Power
Generation/ATWS?
A. Unit 2 Unit Supervisor;
Go to 1-E-1, Loss of Reactor or Secondary Coolant.
B. Unit 2 Unit Supervisor;
Return to 1-E-O, Reactor Trip or Safety Injection.
C. Shift Manager;
Go to 1-E-1, Loss of Reactor or Secondary Coolant.
D. Shift Manager;
Return to 1-E-O, Reactor Trip or Safety Injection.
95
North Anna Power Station
2008 SRO Exam
96.
Given the following:
Unit 1 is operating at 100% power.
The following alarm is received several times in a 10 minute period:
1D-H5, HIGH CAPACITY S/G BLOWDOWN TROUBLE
Local indication at the High Capacity S/G Blowdown Control Panel is normal.
The Instrument Technician investigating the alarm determines that the
comparator card for the annunciator is failing.
A replacement comparator card is unavailable and assistance has been
requested from Engineering.
To restore functionality of the alarm in the interim a jumper must be installed.
Which ONE of the following procedures will govern the installation of the jumper, and
who, by title, must provide FINAL approval of the jumper?
A. OP-NA-200-1 001, Equipment Clearance Process; FSRC (formerly known as
SNSOC).
B. VPAP-1403, Temporary Modifications; Shift Manager.
C. OP-NA-200-1 001, Equipment Clearance Process; Shift Manager.
D. VPAP-1403, Temporary Modifications; FSRC (formerly known as SNSOC).
96
North Anna Power Station
2008 SRO Exam
97.
Given the following:
A Unit 1 RCS heatup is in progress.
RCS Tave is 342°F.
1H Emergency Diesel Generator is declared INOPERABLE due to failure of the
Shutdown Relay.
current
Which ONE of the following identifies (1) thefOPERATIONAL MODE and (2) the
Technical Specification requirements to enter the next higher Mode?
A. (1)
(2)
B. (1)
(2)
.C. (1)
(2)
D. (1)
(2)
Mode 3
Change to Mode 2 may be performed provided the TS 3.8.1, AC Sources -
Operating, Action Statements for 1H EDG inoperability are satisfied. Risk
evaluation and NRC approval is NOT required.
Mode 4
Change to Mode 3 may be NOT performed without a risk evaluation and
approval from the NRC.
Mode 3
Change to Mode 2 may be NOT performed without a risk evaluation and
approval from the NRC.
Mode 4
Change to Mode 3 may be performed provided the TS 3.8.1, AC Sources -
Operating, Action Statements for 1H EDG inoperability are satisfied. Risk
evaluation and NRC approval is NOT required.
97
North Anna Power Station
2008 SRO Exam
98.
Which ONE of the following describes the Release Permit approval process in
accordance with 0-OP-23.3, Waste Gas Decay Tanks & Waste Gas Diaphram
Compressors, AND also identifies the Technical Specification Bases for the maximum
radioactivity content in each gas storage tank?
A. Operations initiates the release request and Health Physics (HP) authorizes the
release permit;
an individual at the exclusion boundary will not exceed 0.5 rem total body exposure
in the event of an uncontrolled release of a tanks contents.
B. Chemistry initiates the release request and Health Physics (HP) authorizes the
release permit;
an individual at the exclusion boundary will not exceed 0.5 rem total body exposure
in the event of an uncontrolled release of a tanks contents.
C. Chemistry initiates the release request and Health Physics (HP) authorizes the
release permit;
an individual at the exclusion boundary will not exceed 0.1 rem total body exposure
in the event of an uncontrolled release of a tanks contents.
D. Operations initiates the release request and Health Physics (HP) authorizes the
release permit;
an individual at the exclusion boundary will not exceed 0.1 rem total body exposure
in the event of an uncontrolled release of a tanks contents.
98
99.
North Anna Power Station
2008 SRO Exam
Initial conditions:
Unit 1 is in Mode 3 shutting down for a scheduled refueling.
A fire is in progress in the Motor Driven AFW Pump House.
The Fire Brigade is at the scene.
Current conditions:
The fire was burning for 12 minutes and is now extinguished.
The 1B MDAFW Pump motor was destroyed by the fire.
Which ONE of the following describes the impact on Safe Shutdown Functions, and
whether E-Plan action is required in accordance with O-FCA-O, Fire Protection -
Operations Response?
A. The Reactor Heat Removal function required to get from Mode 4 to Mode 5 is
affected;
EPIP 1.01, Emergency Manager Controlling Procedure is NOT required to be
implemented.
B. The Reactor Heat Removal function required to get to Mode 4 is affected;
EPIP 1.01, Emergency Manager Controlling Procedure is required to be
implemented.
C. The Reactor Heat Removal function required to get to Mode 4 is affected;
EPIP 1.01, Emergency Manager Controlling Procedure is NOT required to be
implemented.
D. The Reactor Heat Removal function required to get from Mode 4 to Mode 5 is
affected;
EPIP 1.01, Emergency Manager Controlling Procedure is required to be
implemented.
99
100.
North Anna Power Station
2008 SRO Exam
A LOCA has occurred on Unit 1.
RCS pressure indicates 190 psig and stable.
RCS temperature is 260 degrees F and lowering.
Containment pressure is 27 psia.
Low Head SI flow indicates 1200 gpm on each train.
All equipment is operating as designed.
The crew has just entered 1-ES-1.3, Transfer to Cold Leg Recirculation.
The STA reports a RED path on the INTEGRITY CSF Status Tree.
Given these plant conditions, which ONE of the following describes the hierarchy of
requried procedure actions?
A. Remain in 1-ES-1.3 until transfer to Cold Leg Recirculation is complete through
step 8;
Transition to 1-FR-P.1 and verify that RCS pressure is below the Low Head SI
pump shutoff head, then return to 1-ES-1.3.
B. Remain in 1-ES-1.3 until transfer to Cold Leg Recirculation is complete through
step 8;
Transition to 1-FR-P.1 and perform the actions to stop the RCS cooldown, then
return to 1-ES-1.3.
C. Immediately transition to 1-FR-P.1, Response to Imminent Pressurized Thermal
Shock;
Verify that RCS pressure is below the Low Head SI pump shutoff head and then
return to 1-ES-1.3.
D. Immediately transition to 1-FR-P.1, Response to Imminent Pressurized Thermal
Shock;
Perform the actions of 1-FR-P.1 to stop the RCS cooldown and then return to
1-ES-1.3.
100
RTS Instrumentation
3.3.1
3.3
INSTRUMENTATION
3.3.1
Reactor Trip System (RTS) Instrumentation
The RTS instrumentation for each Function in Table 3.3.1-1
shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.1-1.
ACTIONS
- - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each Function.
CONDITION
REQUIRED ACTION
COMPLETION TIME
A.
One or more Functions
A.1
Enter the Condition
Immediately
with one or more
referenced in
required channels or
Table 3.3.1-1 for the
trains inoperable.
channel (s) or
train(s).
B.
One Manual Reactor
B.1
Restore channel to
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
Trip channel
OPERABLE status.
-
B.2
Be in MODE 3.
54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />
C.
One channel or train
C.1
Restore channel or
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
train to OPERABLE
status.
-
C.2.1
Initiate action to
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
fully insert all rods.
AND
(continued)
-
North Anna Units 1 and 2
3.3.1-1
Amendment 231/212
ACTIONS
RTS Instrumentation
3.3.1
CONDITION
C.
(continued)
D.
One Power Range
Neutron Flux-High
channel inoperable.
REQUIRED ACTION
C.2.2
Place the Rod Control
System in a condition
incapable of rod
withdrawal.
NOTE-------------
The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing and
setpoint adjustment of other
channels.
COMPLETION TIME
49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />
0.1.1
Place channel in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
AND
0.1.2
Reduce THERMAL POWER
to
~ 75% RTP.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
0.2.1
Place channel in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
AND
NOTE-----------
Only required to be performed
when the Power Range Neutron
Flux input to QPTR is
0.2.2
Perform SR 3.2.4.2.
0.3
Be in MODE 3.
North Anna Units 1 and 2
3.3.1-2
Once per
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
78 hours
Amendment 231/212
ACTIONS
RTS Instrumentation
3.3.1
CONDITION
REQUIRED ACTION
COMPLETION TIME
E.
One channel
NOTE-------------
The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
E.1
Place channel in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
-
E.2
Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
F.
One Intermediate Range
F.1
Reduce THERMAL POWER
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Neutron Flux channel
to < P-6.
-
F.2
Increase THERMAL POWER
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
to > P-10.
G.
Two Intermediate Range
NOTE-------------
Neutron Flux channels
Limited plant cool down or
boron dilution is allowed
provided the change is
accounted for in the
calculated SDM.
G.1
Suspend operations
Immediately
involving positive
reactivity additions.
AND
-
G.2
Reduce THERMAL POWER
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
to < P-6.
North Anna Units 1 and 2
3.3.1-3
Amendment 231/212
ACTIONS
RTS Instrumentation
3.3.1
CONDITION
REQUIRED ACTION
COMPLETION TIME
H.
One Source Range
NOTE-------------
Neutron Flux channel
Limited plant cooldown or
boron dilution is allowed
provided the change is
accounted for in the
calculated SDM.
H.1
Suspend operations
Immediately
involving positive
reactivity additions.
I .
Two Source Range
I .1
Open Reactor Trip
Immediately
Neutron Flux channels
Breakers (RTBs).
J.
One Source Range
J.1
Restore channel to
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
Neutron Flux channel
OPERABLE status.
-
J.2.1
Initiate action to
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
fully insert all rods.
AND
-
J.2.2
Place the Rod Control
49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />
System in a condition
incapable of rod
withdrawal.
North Anna Units 1 and 2
3.3.1-4
Amendment 231/212
ACTIONS
RTS Instrumentation
3.3.1
CONDITION
REQUIRED ACTION
COMPLETION TIME
K.
Required Source Range
NOTE-------------
Neutron Flux channel
Plant temperature changes are
allowed provided the
temperature change is
accounted for in the
calculated SDM.
K.l
Suspend operations
Immediately
involving positive
reactivity additions.
AND
-
K.2
Perform SR 3.1.1.1.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
AND
-
Once per
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
thereafter
L.
One channel
NOTE-------------
The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
L.l
Place channel in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
-
L.2
Reduce THERMAL POWER
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
to < P-7.
North Anna Units 1 and 2
3.3.1-5
Amendment 231/212
ACTIONS
RTS Instrumentation
3.3.1
CONDITION
M.
One Reactor Coolant
Pump Breaker Position
channel inoperable.
REQUIRED ACTION
NOTE-------------
The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
COMPLETION TIME
M.l
M.2
Restore channel to
OPERABLE status.
Reduce THERMAL POWER
to < P-7.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
78 hours
N.
One Turbine Trip
channel inoperable.
NOTE-------------
The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
N.l
Place channel in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
N.2
Reduce THERMAL POWER
to < P-8.
76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br />
O.
One train inoperable.
NOTE-------------
One train may be bypassed for
up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for
surveillance testing provided
the other train is OPERABLE.
0.1
Restore train to
OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
0.2
Be in MODE 3.
North Anna Units 1 and 2
3.3.1-6
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />
Amendment 231/212
ACTIONS
RTS Instrumentation
3.3.1
CONDITION
REQUIRED ACTION
COMPLETION TIME
P.
One RTB train
NOTES------------
1. One train may be bypassed
for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for
surveillance testing,
provided the other train
is OPERABLE.
2. One RTB may be bypassed
for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for
maintenance on
undervoltage or shunt trip
mechanisms, provided the
other train is OPERABLE.
3. One RTB train may be
bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
for concurrent
surveillance testing of
the RTB and automatic trip
logic, provided the other
train is OPERABLE.
P.1
Restore train to
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
OPERABLE status.
-
P.2
Be in MODE 3.
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />
Q.
One or more channels
Q.1
Verify interlock is in
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
required state for
existing unit
conditions.
-
Q.2
Be in MODE 3.
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />
North Anna Units 1 and 2
3.3.1-7
Amendment 231/212
RTS Instrumentation
3.3.1
ACTIONS
CONDITION
REQUIRED ACTION
COMPLETION TIME
R.
One or more channels
R.l
Verify interlock is in
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
required state for
existing unit
conditions.
-
R.2
Be in MODE 2.
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />
S.
One trip mechanism
S.1
Restore inoperable
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
inoperable for one
trip mechanism to
RTB.
OPERABLE status.
-
S.2
Be in MODE 3.
54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />
SURVEILLANCE REQUIREMENTS
- - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - -
Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.
SR
3.3.1.2
SURVEILLANCE
Perform CHANNEL CHECK.
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
after THERMAL POWER is
~ 15% RTP.
FREQUENCY
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
Compare results of calorimetric heat
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
balance calculation to power range channel
output. Adjust power range output if
calorimetric heat balance calculation
result exceeds power range channel output
by more than +2% RTP.
North Anna Units 1 and 2
3.3.1-8
Amendment 231/212
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
RTS Instrumentation
3.3.1
FREQUENCY
SR
3.3.1.4
SR
3.3.1.6
NOTE--------------------
Not required to be performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
after THERMAL POWER is
~ 15% RTP.
Compare results of the incore detector
measurements to Nuclear Instrumentation
System (NIS) AFD. Adjust NIS channel if
absolute difference is
~ 3%.
NOTE--------------------
This Surveillance must be performed on the
reactor trip bypass breaker immediately
after placing the bypass breaker in
service.
Perform TADOT.
Perform ACTUATION LOGIC TEST.
NOTE--------------------
Verification of setpoint is not required.
Perform TADOT.
NOTE-------------------
Not required to be performed for source
range instrumentation prior to entering
MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after
entry into MODE 3.
Perform COT.
31 effective
full power days
(EFPD)
31 days on a
STAGGERED TEST
BASIS
31 days on a
STAGGERED TEST
BASIS
92 days
92 days
North Anna Units 1 and 2
3.3.1-9
Amendment 231/212
RTS Instrumentation
3.3.1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
NOTE--------------------
This Surveillance shall include
verification that interlocks P-6 and P-I0
are in their required state for existing
unit conditions.
FREQUENCY
NOTE-----
Only required
when not
performed wi thi n
previous 92 days
Perform COT.
Pri or to reactor
startup
AND
Four hours after
reducing power
below P-6 for
source range
instrumentation
AND
Twelve hours
after reducing
power below P-I0
for power and
intermediate
range
instrumentation
AND
Once per 92 days
thereafter
NOTES-------------------
1. Adjust NIS channel if absolute
difference
~ 3%.
2. Not required to be performed until
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after THERMAL POWER is
~ 50% RTP.
Compare results of the excore channels to
incore detector measurements.
92 EFPD
North Anna Units 1 and 2
3.3.1-10
Amendment 231/212
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
SR 3.3.1.10
NOTE--------------------
This Surveillance shall include
verification that the time constants are
adjusted to the prescribed values.
Perform CHANNEL CALIBRATION.
SR 3.3.1.11
NOTE--------------------
Neutron detectors are excluded from CHANNEL
CALIBRATION.
Perform CHANNEL CALIBRATION.
SR 3.3.1.12
Perform CHANNEL CALIBRATION.
SR 3.3.1.13
Perform COT.
RTS Instrumentation
3.3.1
FREQUENCY
18 months
18 months
18 months
18 months
SR 3.3.1.14
NOTE--------------------
Verification of setpoint is not required.
Perform TADOT.
SR 3.3.1.15
NOTE--------------------
Verification of setpoint is not required.
Perform TADOT.
18 months
Prior to
exceeding the
P-8 interlock
whenever the
unit has been in
MODE 3, if not
performed wi thi n
the previous
31 days
North Anna Units 1 and 2
3.3.1-11
Amendment 231/212
RTS Instrumentation
3.3.1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
SR 3.3.1.16
NOTE--------------------
Neutron detectors are excluded from
response time testing.
FREQUENCY
Verify RTS RESPONSE TIME is within limits.
18 months on a
STAGGERED TEST
BASIS
North Anna Units 1 and 2
3.3.1-12
Amendment 231/212
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 1 of 5)
Reactor Trip System Instrumentation
FUNCTION
APPLICABLE MODES
OR OTHER
SPECIFIED
REQUIRED
SURVEILLANCE
CONDITIONS
CHANNELS
CONDITIONS
REQUIREMENTS
ALLOWABLE VALUE
2. Power Range Neutron Flux
1, 2
3(a), 4(a), 5(a)
2
2
B
C
SR 3.3.1.14
SR 3.3.1.14
NA
NA
a.
Hi gh
b. Low
3. Power Range Neutron Flux Rate
1, 2
4
4
D
E
- 110% RTP
SR
3.3.1.3
SR
3.3.1.11
SR 3.3.1.16
- 26% RTP
SR
3.3.1.11
SR 3.3.1.16
a. High Positive Rate
b. High Negative Rate
4. Intermediate Range Neutron Flux
5. Source Range Neutron Flux
1, 2
1, 2
4
4
2
2
E
E
F, G
H, I
SR
3.3.1.11
SR
3.3.1.11
SR 3.3.1.16
SR
3.3.1.8
SR 3.3.1.11
SR
3.3.1.8
SR 3.3.1.11
SR 3.3.1.16
- 5.5% RTP
with time
constant
~ 2 sec
- 5.5% RTP
with time
constant
~ 2 sec
- 40% RTP
- 1.3 E5 cps
NA
2
I, J
K
- 1.3 E5 cps
SR
3.3.1.11
SR 3.3.1.16
SR
3.3.1.11
(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(b) Below the P-I0 (Power Range Neutron Flux) interlocks.
(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.
(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(e) With the Rod Control System incapable of rod withdrawal. In this condition, source range Function does
not provide reactor trip but does provide indication.
North Anna Units 1 and 2
3.3.1-13
Amendment 231/212
PC~f~T
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 2 of 5)
Reactor Trip System Instrumentation
APPLICABLE MODES
OR OTHER
SPECIFIED
REQUIRED
SURVEILLANCE
FUNCTION
CONDITIONS
CHANNELS
CONDITIONS
REQUIREMENTS
ALLOWABLE VALUE
6. Overtemperature
~T
1, 2
3
E
Refer to
Note 1 (Page
3.3.1-16)
SR
3.3.1.12
SR 3.3.1.16
7. Overpower
~T
1, 2
3
E
Refer to
Note 2 (Page
SR 3.3.1.12
3.3.1-17)
8. Pressurizer Pressure
a.
Low
1(f)
3
L
~ 1860 psig
SR
3.3.1.10
SR 3.3.1.16
b. Hi gh
1, 2
3
E
~ 2370 psig
SR
3.3.1.10
SR 3.3.1.16
9. Pressurizer Water Level-High
1(f)
3
L
~ 93%
SR
3.3.1.10
SR 3.3.1.16
10. Reactor Coolant Flow-Low
1(f)
3 per
L
~ 89%
loop
SR
3.3.1.10
SR 3.3.1.16
11. Reactor Coolant Pump (RCP)
1(f)
1 per
M
SR 3.3.1.14
NA
Breaker Position
12. Undervoltage RCPs
1(f)
1 per
L
~ 2870 V
bus
SR 3.3.1.10
SR 3.3.1.16
13. Underfrequency RCPs
1(f)
1 per
L
SR 3.3.1.6(9)
~ 56 Hz
bus
SR 3.3.1.10
SR 3.3.1.16
14. Steam Generator (SG) Water
1, 2
3 per SG
E
~ 17%
Level-Low Low
SR
3.3.1.10
SR 3.3.1.16
(f)
Above the P-7 (Low Power Reactor Trips Block) interlock.
(g) Required to be performed for Unit 2 only.
North Anna Units 1 and 2
3.3.1-14
Amendment 231/212
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 3 of 5)
Reactor Trip System Instrumentation
FUNCTION
15. SG Water Level-Low
Coincident with Steam
Flow/Feedwater Flow Mismatch
APPLICABLE MODES
OR OTHER
SPECIFIED
CONDITIONS
1, 2
1, 2
REQUIRED
CHANNELS
2 per SG
2 per SG
SURVEILLANCE
CONDITIONS
REQUIREMENTS
E
SR
3.3.1.7
SR 3.3.1.10
E
SR
3.3.1.7
SR 3.3.1.10
ALLOWABLE VALUE
~ 24%
~ 42.5% full
steam flow at
16. Turbine Trip
a. Low Auto Stop Oil Pressure
b. Turbine Stop Valve Closure
17. Safety Injection (SI) Input
from Engineered Safety Feature
Actuation System (ESFAS)
lB. Reactor Trip System Interlocks
a. Intermediate Range Neutron
Flux, P-6
b. Low Power Reactor Trips
Block, P-7
c. Power Range Neutron Flux,
P-B
d. Power Range Neutron Flux,
P-10
e. Turbine Impulse Pressure,
P-13
19. Reactor Trip Breakers(i)
20. Reactor Trip Breaker
Undervoltage and Shunt Trip
Mechanisms
21. Automatic Trip Logic
1, 2
1, 2
1, 2
3(a), 4(a), 5(a)
1, 2
1, 2
3(a), 4(a), 5(a)
3
4
2 trains
2
1 per
train
4
4
2
2 trains
2 trains
1 each
per RTB
1 each
per RTB
2 trains
2 trains
N
N
o
Q
R
R
Q
R
P
C
S
C
o
C
SR 3.3.1.10
SR 3.3.1.15
SR 3.3.1.10
SR 3.3.1.15
SR 3.3.1.14
SR 3.3.1.11
SR 3.3.1.13
SR
3.3.1.11
SR 3.3.1.13
SR 3.3.1.11
SR 3.3.1.13
SR 3.3.1.10
SR 3.3.1.13
SR
3.3.1.4
SR
3.3.1.4
SR
3.3.1.5
~ 40 psig
~ 0% open
NA
~ 3E-11 amp
NA
~ 31% RTP
~ 7% RTP
~ 11% RTP
~ 11% turbi ne
power
NA
NA
NA
NA
NA
NA
(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(h) Above the P-B (Power Range Neutron Flux) interlock.
(i)
Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.
North Anna Units 1 and 2
3.3.1-15
Amendment 231/212
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 4 of 5)
Reactor Trip System Instrumentation
Note 1: Overtemperature
~T
The Overtemperature ~T Function Allowable Value shall not exceed the
following nominal trip setpoint by more than 2.0% of
~T span.
~T :s; ~To{ K1- K2~ ~ : :~: ~ [T- T'] + K3(P - PI)- f 1(~I)}
Where:
~T is measured RCS
~T, OF.
~To is the indicated
~T at RTP, OF.
s is the Laplace transform operator, sec-I.
T is the measured RCS average temperature, OF.
T
I is the nominal Tavg at RTP,
~ [*]OF.
P is the measured pressurizer pressure, psig
pi is the nominal
RCS operating pressure,
~ [*] psig
KI ~ [*]
K2
~ [*]/oF
K3
~ [*]/psig
~I
~ [*] sec
~2
~ [*] sec
f 1(~I) = [*] {[*] - (q, - qb)}
when qt - qb < [*] % RTP
0
when [*]% RTP
~ qt - qb
~ [*]% RTP
[*] {(qt - qb) - [*]}
when qt - qb > [*]% RTP
Where qt and qb are percent RTP in the upper and lower halves
of the core, respectively, and qt + qb is the total
THERMAL
POWER in percent RTP.
The values denoted with [*] are specified in the COLR.
North Anna Units 1 and 2
3.3.1-16
Amendment 245/226
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 5 of 5)
Reactor Trip System Instrumentation
Note 2: Overpower L1T
The Overpower
L1T Function Allowable Value shall
not exceed the following
nominal trip setpoint by more than 2% of
~T span.
Where:
~T is measured RCS
~T, OF.
~To is the indicated L1T at RTP, OF.
s is the Laplace transform operator, sec-I.
T is the measured RCS average temperature, OF.
T
I is the nominal Tavg at RTP,
~ [*]OF.
K4
~ [*]
K5 ~ [*]jOF for increasing Tavg
[*]jOF for decreasing Tavg
K6
~ [*]jOF when T > T
I
[*]jOF when T ~ T
I
The values denoted with [*] are specified in the COLR.
North Anna Units 1 and 2
3.3.1-17
Amendment 231/212
Spent Fuel Pool Storage
3.7.18
45000 .....---.....--........----.,---.......--.......---.------.--......
4.6
4.2
3.8
Unacceptable
3.4
3
2.6
2.2
Acceptable
1.8
O-t------+--------+---~~--......--_+_--_+_--_+--__t
1.4
15000 +-----+------+----#-----1---+----1---+-----+----+-----1
10000 -I-----t-----#----+------I-'l---+-----+-----+-----+------I
30000 +----t-------+------I---+------#------+-----+--.'---I
35000 +-----+------+------1---+-----+-----r..l~-----+-------I
5000 +----.------+-----:lIl~---li_---f----+------+-----+-----1
40000 +----t-------+------I---+-----+------+-----+-#------II
5'
I-:E
C3:
~ 25000 +----t-------+------I----#-----+------+-----#---+------II
Q,
- se'-
- sco
~:c
E
20000 +----t-------+------I-#---+-----+---#-----+-----+------II
Q)tntn<<-;
- s
u,
Initial U-235 Enrichment (nominal w/o)
Acceptable: Acceptable for storage in non-matrix location or low reactivity location in matrix
configuration. May also be placed in high reactivity locations in matrix configuration.
Conditionally Acceptable: Acceptable for storage in non-matrix location, but must be placed
in high reactivity location if stored in matrix configuration.
Unacceptable: Must be stored in high reactivity location in matrix configuration. Surry spent
fuel must be stored in high reactivity locations in a matrix.
Figure 3.7.18-1 (page 1 of 1)
Burnup Credit Requirements
North Anna Units 1 and 2
3.7.18-3
Amendments 231/212
Inverters-Operating
3.8.7
3.8
ELECTRICAL POWER SYSTEMS
3.8.7
Inverters-Operating
The Train H and Train J inverters shall be OPERABLE.
- - - - - - - - - - - - NOTE - - - - - - - - - - - -
One inverter may be disconnected from its associated DC bus
for
~ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform an equalizing charge on its
associated battery, provided:
a. The associated AC vital bus is energized from its constant
voltage source transformer; and
b. All other AC vital buses are energized from their
associated OPERABLE inverters.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS
CONDITION
REQUIRED ACTION
COMPLETION TIME
A.
One inverter
A.1
NOTE--------
Enter applicable
Conditions and
Required Actions of
IIDistribution
Systems-Operatinq"
with any vital bus
de-energized.
Restore inverter to
7 days
OPERABLE status.
B.
Required Action and
B.1
Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
associated Completion
Time not met.
AND
-
B.2
Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
North Anna Units 1 and 2
3.8.7-1
Amendments 235/217
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
Inverters-Operating
3.8.7
FREQUENCY
Verify correct inverter voltage and
alignment to required AC vital buses.
7 days
North Anna Units 1 and 2
3.8.7-2
Amendments 231/212
Distribution Systems-Operating
3.8.9
3.8
ELECTRICAL POWER SYSTEMS
3.8.9
Distribution Systems-Operating
The following distribution subsystems shall be OPERABLE:
a. The Train H and Train J AC, DC, and AC vital buses; and
b. One AC and DC bus on the other unit for each required
shared component.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS
CONDITION
A.
One or more
electrical power
distribution
subsystem(s)
North Anna Units 1 and 2
A.l
REQUIRED ACTION
NOTE--------
Enter applicable
Conditions and
Required Actions of
IIDC
Sources-Operating, II
for DC train(s) made
inoperable by
distribution
subsystem(s).
Restore AC electrical
power distribution
subsystem(s) to
OPERABLE status.
3.8.9-1
COMPLETION TIME
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
AND
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from
discovery of
failure to meet
LCO
Amendments 231/212
ACTIONS
Distribution Systems-Operating
3.8.9
CONDITION
REQUIRED ACTION
COMPLETION TIME
B.
One or more
B.1
Restore AC vital bus
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
LCO 3.8.9.a AC vital
subsystem(s) to
bus(es) inoperable.
OPERABLE status.
AND
-
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from
discovery of
failure to meet
LCO
C.
One or more
C.1
Restore DC electrical
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
power distribution
electrical power
subsystem(s) to
AND
distribution
OPERABLE status.
-
subsystem(s)
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from
discovery of
failure to meet
LCO
D.
NOTE----------
D.1
Declare associated
Immediately
Separate Condition
shared component(s)
entry is allowed 'for
each AC subsystem.
One or more required
electrical power
distribution
subsystem(s)
E.
NOTE----------
E.1
Declare associated
Immediately
Separate Condition
shared component(s)
entry is allowed for
each DC subsystem.
One or more required
electrical power
distribution
subsystem(s)
North Anna Units 1 and 2
3.8.9-2
Amendments 231/212
Distribution Systems-Operating
3.8.9
ACTIONS
CONDITION
REQUIRED ACTION
COMPLETION TIME
F.
Required Action and
F.1
Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
associated Completion
Time for Condition A,
AND
B, or C not met.
-
F.2
Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
G.
Two or more
G.1
Enter LCO 3.0.3.
Immediately
LCO 3.8.9.a electrical
power distribution
subsystems inoperable
that result in a loss
of safety function.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
Verify correct breaker alignments and
voltage to required AC, DC, and AC vital
bus electrical power distribution
subsystems.
FREQUENCY
7 days
North Anna Units 1 and 2
3.8.9-3
Amendments 231/212
GENERIC FUNDAMENTALS EXAMINATION
EQUATIONS AND CONVERSIONS HANDOUT SHEET
EQUATIONS
Q = milh
Q = UAilT
. 3
Q oc
mNat Cire
ilT ec
th~at Cire
p = (Keff - 1)/Keff
SUR = 26.06/-17
13eff
- p
't =---
Aeff p
Q*
13eff
p=-+---
r
1 + Aeff r
Q*= 1 x 10-4 sec
Aeff = 0.1 sec" (for small positive p)
2
2
DRW oc <Ptip/ <Pavg
P = P 10SUR(t)
o
P = P e(th)
o
A = A e-At
o
F=PA
ill = pAy
W
- milPu
Pump
-
E=IR
Thermal Efficiency = Net Work Out/Energy In
g(Z2 - ZI) + (V22- "12) + u(P2- PI) + (u2 - u.) + (q - w) = 0
gc
2gc
gc = 32.2 lbm-ft/lbf-sec'
CONVERSIONS
1 Mw = 3.41 X 106 Btu/hr
1 Curie = 3.7 x 1010 dps
1 hp
= 2.54 x 103 Btu/hr
1 kg
= 2.21 Ibm
1 Btu
= 778 ft-lbf
1 galwater = 8.35 Ibm
°C
= (5/9)(OF - 32)
1 Wwater = 7.48 gal
OF
= (9/5)(OC)+ 32
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