ML082390017
| ML082390017 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/22/2008 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| ER-08-301 | |
| Download: ML082390017 (129) | |
See also: IR 05000338/2008301
Text
Final Submittal
NORTH ANNA JUNE 2008 EXAM 05000338/2008301
&05000339/2008301
FINAL SRO WRITTEN EXAMINATION
AND REFERENCES
0/--
kEy c:£-AI 4-5
NORTH ANNA 2008 RO/SRO WRITTEN EXAM LIST OF KIA's&EXAM ANSWER KEY*FINAL Page 1 of 3'.1 0;, , 1 00102.4,31
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B 30 032 AK3.0130 C 31 033 K4.05 31 D 32 036 AAl.Ol 32 D 33 03902.1.3233
B 34 04 I K:6.03 34 D 35 054 AD.OJ 35 C 36 055 AJ.03 36 A 37 OSS BAl.06 37 A 38 056 AA2.72 38 A 39 057 02.4.45 39 A 40 058 AKI.OJ 40 B 41 059 KI.02 4J C 42 060 AA2.05 42 C 43 06102.4.343
A 44 061 K2.01 44 A
NORTH ANNA 2008 RO/SRO WRITTEN EXAM LIST OF KJA's&EXAM ANSWER KEY*FINAL Page 2 of 3 45 06202.1.2745
A 46 06210.0346
A 47 063 K4.0147 D 48 06410.0248
D 49 065 AK3.03 49 B SO 071
A 51 073 ALai 51 D 52 073 KS.02 52 D S3 976 AI.9i!S3 C
S4 076 AK2.01 54 C 55 077 AAl.OI 55 D 56 078 A4.01 56 C 57 078 K4.03 57 A 58 079 Kl.OI 58 C 59 103 A3.01 59 D 60 E03 EA1.2 60 D 61 EOS EK3.4 61 D 62 899 EA2.162 D 63 EI2 EK2.I 63 C 64 EI5 EK2.I 64 D 65 E16EIO.l6S
A 66 02.1.2066 A 67 02.1.3767 C 68 02.1.4168 D 69 02.2.1 69 A 70 02.2.3970 A 71 02.2.771 B 72 02.3.15 f?C 13 02.3.4 73 C 74 02.4.3274 B 15 02.4.975 A 16 005 AA2.02 76 A 17 OOS 02.2.40 77 D 78 006A2.0378
D 79 007 02.2.44 79 C 80 008 02.4.8 80 B 81 012 A2.04 81 D'82 017 A2.02 82 B 83 025 AA2.03 83 C 84 02602.1.784
C 8S 027 02.2.25 85 A 86 034 A2.03 86 B 87 038 EA2.IS 87 A 88 OSI 02.2.44 88 C
NORTH ANNA 2008 RO/SRO WRITTEN EXAM LIST OF KIA's&EXAM ANSWER KEY*FINAL Page 3 of3 89 056 G2.2.36 89 90 05907*1.23
90 91 061 AA2.04 91 92 062 AA2.05 92 93 E13 02.4.2093 94 02.1.494 95 02.1.695 96 02.2.11 96 97 02.2.35 97 98 02.3.698 99 02.4.27 99 100 02.4.6 100 A C o-&-A A B B-&-B B A B A
ES-401 Site-Specific
SRO Written Examination
Cover Sheet Form ES-401-8 U.s.Nuclear Regulatory
Commission
Site-Specific
SRO Written Examination
Applicant Information
Name: Date: June 24, 2008 Facility/Unit:
North Anna/Units1&2 Region: II Reactor Type: Westinghouse
Start Time: Finish Time: Instructions
Use the answer sheets provided to document your answers.Staple this cover sheet on top of the answer sheets.To pass the examination
you must achieve a final grade of at least 80.00 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'sSignature
Results RO/SRO-OnlylTotal
Examination
Values--/--/--Points Applicant's
Scores--/--/--Points Applicant's
Grade--/--/--Percent
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 2.5 0 F 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.
- 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.1 H1;breaker is open.C.1 H1;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 74%and INCREASING
SLOWLY.*PRT pressure is 12 psig and INCREASING
SLOWLY.*PRT temperature
is 132°F and INCREASING
SLOWLY.*The following annunciators
are LIT: 1 B-H1, PRZ RELIEF TK HI TEMP*1 B-G2, PRZ SAFETY W LINE HI TEMP*1 B-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 themethodused
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.B.SG PORVs;1005 psig.C.SG PORVs;1035 psig.D.Condenser Steam Dumps;1005 psig.8
North Anna Power Station2008SRO Exam 9.Given the following:
Unit 1 is at 100%power.*CC Pump 1A is running and CC Pump1B is in standby.*4160 V Bus1H normal feeder is inadvertantly
opened.Which ONE of the following describes the AUTOMATIC operation of CC Pumps for this event?A.CC Pump1B starts 15 to 20 seconds after Bus1H is reenergized;
CC Pump 1A does NOT re-start.B.CC Pump 1B starts when Bus1H is deenergized;
CC Pump 1A starts as soon as Bus1H is reenergized.
C.CC Pump1B starts 15 to 20 seconds after Bus1H is reenergized;
CC Pump 1A starts 15 to 20 seconds after Bus1H is reenergized.
D.CC Pump1B starts when Bus1H is deenergized;
CC Pump 1A restarts 15to20 seconds after Bus1H 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 psigandstable.
- Core Exit TCs-500 degrees F.RVLlS 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 m'inutes;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%.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 50%.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+5R1hr.Current Plant parameters
are as follows:*RCS temperature
is slowly trending down.*All SGs are 15%Narrow Range and rising.*AFW flow to each SG is 150 gpm.*Containment
pressure is 16 psia and slowly trending down.*Containment
radiation is 1 E+4R1hr and slowly trending down.Which ONE of the following identifies
the AFW flow requirements
in accordance
with 1-E-O, 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.*RCP1B No.1 Seal DP indicates 220 psid and stable.*Annunciator
1C-G2, RCP 18 STANDPIPE HI LEVEL is NOT LIT.*Sealleakoff
has lowered on RCP 1A and 1 C.*Seal Return temperature
is rising slowly.Which ONE of the following identifies
the RCP sealproblem,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 RCP, and isolate sealleakoff
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 ChanneI1-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.*18 Charging Pump is running.*80TH LHSI Pumps are tripped.RCPs are running.RCS pressure is 1600 psig and lowering.*Containment
pressure peaked at 21 psi a 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.8.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 inadequate
to ensure adequate core cooling.18
North Anna Power Station 2008 SRO Exam 19.Given the following:
Unit 1 is at 100%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
AirRecircFans.
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
AirRecircFans.
19
North Anna Power Station 2008 SRO Exam 20.Given the following:
- Unit 1 is at 100%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 DATC notes the following:
- RHR Pump 1A motor amps indicate 10 and stable.1-RH-FCV-1605
in automatic indicates 100%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 psigandstable.
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.8.COA is required;manually actuate COA, stop RCPs, verify Quench Spray running, and verify Containment
Isolation Phase 8.C.COA is not required, however Quench Spray is required;openQuench
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 8, and stop Reps.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-L1-101
is 50%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.*CDA was automatically
actuated 7 minutes ago.*RCS pressure is 1125 psig.RWST level is 72%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 1 J.D.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 PORVBlockValve, 1-RC-MOV-1536, and pressure is now 21 00 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 100%.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.Place2-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 100%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
is in progress on each unit in preparation
for Containment
entry.WI+h bo+h plJr?Je sV'fpl'f
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 approximately3E-11 amps and trending up.*Source Range Channel N-31 indicates 1X10 3 CPS and is trending down slowly.*Source Range Channel N-32 indicates approximately
6X10 3 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 MANUAL.*All other controls are in AUTO.*A Turbine control valve failure results in a load rejection.
- Tavg-Trefdeviationindicates
11 degrees F.*1 M-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.8.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%.1B MFW Pump is out of service for pump coupling repairs.*The following alarms are received:*1 F-A4, MAIN FD PPS DISCH HDR LO PRESS*1F-A5, MAIN FD PP 1A-1B-1C AUTO TRIP*1 F-FlIF2/F3, SG 1A11 B/1 C LEVEL ERROR*1F-D1/D2/D3, STM GEN 1A11B/1C FW<STM FLOW CH III-IV*The BOP determines
that1C 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
North Anna Power Station 2008 SRO Exam 36.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:
Reactor Trip.*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;steamsupply
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 Station2008SRO 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 EDG1J are in progress.*RCP Seal Water Outlet temperature
is 200 0 F and rising at 2°F 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 start1J EDG in MANUALLOCAL.C.Perform Attachment
3, RCP seal isolation, prior to attempting
to start1J EDG in MANUAL-LOCAL.D.Place1J EDG in MANUAL-REMOTE, press EMER GEN Alarm&Shutdown RESET Button, and verify Shutdown Relay Status Light is lit.After one minute, place1J 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 on1H 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;
AFW will be supplied to B SG.B.1-FW-P-3B starts approximately
20 seconds after the 4160 Volt emergency bus is energized;
AFW will be supplied to C SG.C.1-FW-P-3B starts approximately
20 seconds after the 4160 Volt emergency bus is energized;
AFW will be supplied to B SG.D.1-FW-P-3B starts as soon as the 4160 Volt emergency bus is energized;
AFW will be supplied to C SG.38
North Anna Power Station2008SRO 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 1-11I TROUBLE*Battery Charger 1-111 DC Output breaker has tripped and CANNOT be reset.*DC Bus 1-11I voltage is118volts and lowering.Which ONE of the following describes the action that will be taken to restore DC Bus 1-11I in accordance
with 1-0P-26.4.3, Main Station Swing Battery Chargers 1C-1 and 1 C-II Operation?
A.Place Swing Battery Charger 1 C-I in service with the NORMAL/EQUALIZE
switch in EQUALIZE.B.Place Swing Battery Charger 1 C-II in service with the NORMAL/EQUALIZE
switch in NORMAL.C.Place Swing Battery Charger 1 C-II in service with the NORMAL/EQUALIZE
switch in EQUALIZE.D.Place Swing Battery Charger 1 C-I in service with the NORMAL/EQUALIZE
switch in NORMAL.40
North Anna Power Station2008SRO Exam 41.Given the following:
- The plant is at 25%power.*A Condensate
header rupture occurs, and the following conditions
are present:*All Main Feedwater pumps tripped.*10 seconds later SG levels are 30%narrow range and lowering.*Reactor power remains at 25%.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 Tank1B 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&BHIHI 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
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-1DDA, B, C?A.MCC 1J1-2N B.1A Semi-Vital
Bus C.1B Semi-Vital
North Anna Power Station 2008 SRO Exam 45.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.2-11I and 2-IV D.1-1 and 1-11 46
North Anna Power Station 2008 SRO Exam 47.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.Giventhefollowing:*A lightning strike has occurred resulting in a loss of the North Anna Switchyard.
- The1J 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 51.Which ONE of the following describes the reason that no J Train E5F 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 to1J 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:*1 F-F8, SAND FL TR 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 1 B.*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-101, 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.!.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.!.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
North Anna Power Station 2008 SRO Exam 52.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
1 K-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;
1 K-D2 will remain LIT solid.B.240 mRem/hour;
1 K-D2 will remain LIT solid.C.120 mRem/hour;
1 K-D2 will blink and horn will sound until acknowledged.
D.240 mRem/hour;
1 K-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 eirc 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%power.*The B SG has developed a 60 gpd tube leak.*Operators are preparing to shutdown the Unit due to fuel failure resulting in RCS 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.8.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-1 02A or 1-IA-TV-1 02B, 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-102A
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-O, 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-1 02A, 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
North Anna Power Station 2008 SRO Exam 61.Initial Conditions:
- Unit 1 tripped from 100%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%and slowly lowering.*RCS Hot Leg Temperatures
are 560 0 F and slowly lowering.*Core Exit TCs are 565 0 F 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 109°F/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>11%.B.Total flow is maintained
>340 gpm until ALL SG narrow range levels are>11%.C.Flow is reduced to 100 gpm to each SG, and narrow range level in ALL SG's is controlled
at less than 50%.D.Flow is reduced to 100 gpm to each SG, and narrow range level in ALL SG'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 CO NT 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
North Anna Power Station 2008 SRO Exam 67.In accordance
with OP-AP-300, Reactivity
Management, reactor power is required to be reduced below 100%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 J 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 DPM 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.D.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
1 K-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
theEPIP4.04 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 100%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 Pump1B 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
North Anna Power Station 2008 SRO Exam 76.Initial conditions:*A spurious TurbineRunbackoccurred
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 58%.*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?A.72 SPM;H-8 is OPERABLE.B.64 SPM;H-8 is INOPERABLE.
C.72 SPM;H-8 is INOPERABLE.
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 with1B RHR pump in standby.*An electrical
fault on1H 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 abovethetop 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 abovethetop 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: Pressure 1A 18 1C 67%72%59%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.Checkvalve
leakage is occurring;
are all operable.B.Vent valve leakage is occurring;
one SI accumulator
is inoperable.
C.Vent valve leakage is occurring;
are all operable.D.Checkvalve
leakage is occurring;
one Sl 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-1 B,"B" Low Head SafetyInjectionPump
is tagged out for maintenance.
- The1H 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 inoperable;
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 inoperable;
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 the1H 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 100%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 to1J Emergency Bus?A.1-E-1, Loss of Reactor or Secondary Coolant;restore power to1J 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 to1J 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.1 K-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.RVLlS Full Range is 27%.*Core Exit TCs are reading 1250 degrees F.*ALL SG NR levels are OFF-SCALE low.*NO source of SG feedhasbeen 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 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 1 B RHR Pump discharge flow and motor amps oscillating.
- The crew isolates known RCSdrainpaths
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 100%power.Unit 2 is in Mode 5.Unit 1 and 2 CC systems are split.*The OATC reports the following alarms and indications:
1 G-E8, COMP COOL PP1B AUTO TRIP*1G-B3, CC HX 1A-1B CC OUTLET LO FLOW*1 G-C3, CC HX OUTLET LO PRESS*1 C-C4, RCP 1A-B-C CC THERM BARR HI/LO FLOW 1A-E6, RCP 1B VIBRATION ALERT/DANGER
- RCP Thermal Barrier Heat Exchanger flow indicators
all read 0 GPM.RCP Motor Bearing temperatures
are 1460F 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-O, 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-O, 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 1 B, 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 (3.2%)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
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 atthe 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 0 F*RCS Hot Leg Temperatures
are 3350F*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-1D
AUTO TRIP CW Pump1B motor indicates0amps*CW Pumps 1A, 1C, and 1D 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 fortheseplant
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, InvertersOperating 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, InvertersOperating 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 TCs 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
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
Continuous
HP coverage is required.B.Verify Containment
Ventilation
Isolation;
Core alterations
may NOT continue with 1-RM-RMS-162
C.Verify Control Room Bottled Air dump;Core alterations
may NOT continue with 1-RM-RMS-162
D.Verify Containment
Ventilation
Isolation;
Core alterations
may continue with1-RM-RMS-162inoperable.
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-1B are running.*2-SW-P-1B is DOS.*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 Station2008SRO 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 hours on March 24 BOP*12 hours on February 23 BOP*12 hours on February 22 BOP*12 hours on January 19 BOP*12 hours 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 wee 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.e.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
theunitat 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 f10wpath 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:*1 D-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-200-1001, 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 SourcesOperating, Action Statements
for1H 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 SourcesOperating, Action Statements
for1H 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
North Anna Power Station 2008 SRO Exam 99.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.
- The1B 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 ProtectionOperations
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 Sl 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 Sl 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;Performthe
actions of 1-FR-P.1 to stop the RCS cooldown and then return to 1-ES-1.3.100
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 3.3 INSTRUMENTATION
3.3.1 Reactor Trip System (RTS)Instrumentation
LCO 3.3.1 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 Inmediately
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.inoperable.
OR 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 /> inoperable.
train to OPERABLE status.OR 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-NUCLEAR DESIGN INFORMATION
PORTAL-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 withdrawa1*------------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 to75%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 inoperable.
0.2.2 Perform SR 3.2.4.2.OR 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
-NUCLEAR DESIGN INFORMATION
PORTAL-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 /> OR 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.inoperable.
OR 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 inoperable.
boron dilution is allowed provided the change is accounted for in the calculated
SDM.-----------------------------
G.1 Suspend operations
IlM1ediately
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-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 CONDITION REQUIRED ACTION COMPLETION
TIME H.One Source Range------------NOTE-------------
Neutron Flux channel Limited plant cool down or inoperable.
boron dilution is allowed provided the change is accounted for in the calculated
SDM.-----------------------------
H.I Suspend operations
Immediately
involving positive reactivity
additions.
1.Two Source Range 1.1 Open Reactor Trip Immediately
Neutron Flux channels Breakers (RTBs).inoperable.
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.inoperable.
OR 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
-NUCLEAR DESIGN INFORMATION
PORTAL-ACTIONS RTS Instrumentation
3.3.1 CONDITION REQUIRED ACTION COMPLETION
TIME K.Required Source Range------------NOTE-------------
Neutron Flux channel Plant temperature
changes are inoperable.
allowed provided the temperature
change is accounted for in the calculated
SDM.-----------------------------
K.1 Suspend operations
Irrrnediately
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.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 /> OR 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-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 CDNDITION REQUIRED ACTION COMPLETION
TIME M.One Reactor Coolant------------NOTE-------------
Pump Breaker Position The inoperable
channel may be channel inoperable.
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.-----------------------------
M.1*Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.OR M.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.N.One Turbine Trip------------NOTE-------------
channel inoperable.
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.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 /> OR N.2 Reduce THERMAL POWER 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> to<P-8.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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.OR 0.2 Be in MODE 3.30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> North Anna Units 1 and 2 3.3.1-6 Amendment 231/212
-NUCLEAR DESIGN INFORMATION
PORTAL-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.OR 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.l Verify interlockin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.
required state for existing unit conditions.
OR 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
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION
TIME R.One or more channels R.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 /> inoperable.
required state for existing unit conditions.
OR 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.l 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.OR 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 3.3.1.1 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 is15%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
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 SURVEILLANCE
REQUIREMENTS
SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7 SURVEILLANCE
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 is15%RTP.Compare results of the incore detector measurements
to Nuclear Instrumentation
System (NIS)AFD.Adjust NIS channel if absolute difference
is3%.-------------------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.FREQUENCY 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
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 SURVEILLANCE
REQUIREMENTS
SR 3.3.1.8 SURVEILLANCE
NOTE--------------------
This Surveillance
shall include verification
that interlocks
P-6 and P-I0 are in their required state for existing unit conditions.
FREQUENCY
Only required when not performed wi thi n previous 92 days SR 3.3.1.9 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 difference3%.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 is50%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
-NUCLEAR DESIGN INFORMATION
PORTAL-SURVEILLANCE
REQUIREMENTS
SURVEILLANCE
RTS Instrumentation
3.3.1 FREQUENCY 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
Neutron detectors are excluded from CHANNEL CALI BRA TI ON.18 months Perform CHANNEL CALIBRATION.
18 months SR 3.3.1.12 Perform CHANNEL CALIBRATION.
18 months SR 3.3.1.13 Perform COT.18 months SR 3.3.1.14-------------------NOTE--------------------
Verification
of setpoint is not required.-------------------------------------------
Perform TADDT.18 months SR 3.3.1.15-------------------NOTE--------------------
Verification
of setpoint is not required.Perform TADOT.North Anna Units 1 and 2 3.3.1-11 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 Amendment 231/212
-NUCLEAR DESIGN INFORMATION
PORTAL-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
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 Table 3.3.1-1 (page 1 of 5)Reactor Trip System Instrumentation
APPLICABLE
MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE
FUNCTION CONDITIONS
CHANNELS CONDITIONS
REQUIREMENTS
ALLOWABLE VALUE 1.Manual Reactor Trip 1.2 2 B SR 3.3.1.14 NA 3(0).4(0).5(0)2C SR 3.3.1.14 NA 2.Power Range Neutron Flux a.High 1.2 4 D SR 3.3.1.1:s;110%RTP SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 b.Low 1 (b).2 4 E SR 3.3.1.1:s;26%RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 3.Power Range Neutron Flux Rate a.High Positive Rate 1.2 4 E SR 3.3.1.7:s;5.5%RTP SR 3.3.1.11 with time constant2 sec b.High Negative Rate 1.2 4 E SR 3.3.1.7:s;5.5%RTP SR 3.3.1.11 with time SR 3.3.1.16 constant2 sec 4.Intermediate
Range Neutron Flux 1 (b).2(e)2 F.G SR 3.3.1.1:s;40%RTP SR 3.3.1.8 SR 3.3.1.11 5.Source Range Neutron Flux 2(d)2 H.I SR 3.3.1.1:s;1.3 E5 cps SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 3(0).4(0).5(0)2 I.J SR 3.3.1.1:s;1.3 E5 cps SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 3(e).4(el.5(e)K SR 3.3.1.1 NA 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
-NUCLEAR DESIGN INFORMATION
PORTAL-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
AT 1.23E SR 3.3.1.1 Refer to SR 3.3.1.3 Note 1 (Page SR 3.3.1.7 3.3.1-16)SR 3.3.1.9 SR 3.3.1.12 SR 3.3.1.16 7.Overpower AT 1.2 3 E SR 3.3.1.1 Refer to SR 3.3.1.7 Note 2 (Page SR 3.3.1.12 3.3.1-17)8.Pressurizer
Pressure a.Low 1 (f)3 L SR 3.3.1.11860 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 b.Hi gh 1.2 3 E SR 3.3.1.1 S 2370 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 9.Pressurizer
Water Level-High
1 (f)3L SR 3.3.1.1 S 93%SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 10.Reactor Coolant Flow-Low 1 (f)3 per L SR 3.3.1.189%loop SR 3.3.1.7 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 RCP 12.Undervoltage
RCPs 1 (f)1 per L SR 3.3.1.62870 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 I, 2 3 per SG E SR 3.3.1.117%Level-Low Low SR 3.3.1.7 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
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 Table 3.3.1-1 (page 3 of 5)Reactor Trip System Instrumentation
APPLICABLE
MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE
FUNCTION CONDITIONS
CHANNELS CONDITIONS
REQUIREMENTS
ALLOWABLE VALUE 15.SG Water Level-Low 1,22 per SG E SR 3.3.1.124%SR 3.3.1.7 SR 3.3.1.10 Coincident
with Steam I,22 per SG E SR 3.3.1.1:S 42.5%full F10wfFeedwater
Flow Mismatch SR 3.3.1.7 steam flow at SR 3.3.1.10 RTP 16.Turbine Trip a.Low Auto Stop Oil Pressure 1 (h)3N SR 3.3.1.1040 psig SR 3.3.1.15 b.Turbine Stop Valve Closure 1 (h)4 N SR 3.3.1.100%open SR 3.3.1.15 17.Safety Injection (SI)Input I, 2 2 trains 0 SR 3.3.1.14 NA from Engineered
Safety Feature Actuation System (ESFAS)18.Reactor Trip System Interlocks
a.Intermediate
Range Neutron 2(d)2 Q SR 3.3.1.113E-ll amp Flux, P-6 SR 3.3.1.13 b.Low Power Reactor Trips 1 per R SR 3.3.1.5 NA Block, P-7 train c.Power Range Neutron Flux, 4 R SR 3.3.1.11:S 31%RTP P-B SR 3.3.1.13 d.Power Range Neutron Flux, I, 2 4 Q SR 3.3.1.117%RTP P-10 SR 3.3.1.13:S 11%RTP e.Turbine Impulse Pressure,2R SR 3.3.1.10:S 11%turbi ne P-13 SR 3.3.1.13 power 19.Reactor Trip Breakers(i)
I,22 trai ns P SR 3.3.1.4 NA 3(0), 4(0), 5(0)2 trains C SR 3.3.1.4 NA 20.Reactor Trip Breaker I,21 each S SR 3.3.1.4 NA Undervoltage
and Shunt Trip per RTB Mechanisms
3(0), 4(0), 5(0)1 each C SR 3.3.1.4 NA per RTB 21.Automatic Trip Logic I,22 trai ns 0 SR 3.3.1.5 NA 3(0), 4(a), 5(0)2 trains C SR 3.3.1.5 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-8 (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
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 Table 3.3.1-1 (page 4 of 5)Reactor Trip System Instrumentation
Note 1: Overtemperature The Overtemperature Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2.0%of span.Where: is measured RCS of. is the indicated at RTP, of.s is the Laplace transform operator, sec-l.T is the measured RCS average temperature, OF.T'is the nominal T avg at RTP,[*]OF.P is the measured pressurizer
pressure, psig pI is the nominal RCS operating pressure,[*]psig't2[*]sec K 3[*]/ps i g f l=[*]{[*]-(qt-qb)}o[*]{(qt-qb)-[*]}when qt-qb<[*]0/.7 RTP when[*]%RTPqt-qb[*]0/.7 RTP 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
-NUCLEAR DESIGN INFORMATION
PORTAL-RTS Instrumentation
3.3.1 Table 3.3.1-1 (page 5 of 5)Reactor Trip System Instrumentation
Note 2: Overpower.1T The Overpower.1T Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2%of.1T span.Where:.1T is measured RCS.1T, OF..1T o is the indicated.1T at RTP, OF.s is the Laplace transform operator.sec*I.T is the measured RCS average temperature.
OF.T I is the nominal T avg at RTP.[*]oF.K 4[*]K s[*]jOF for i ncreas i ng T avg[*]jOF for decreasing
T avg K 6[*]/oF when T>T I[*]jOF when TT I The values denoted with[*]are specified in the COLR.North Anna Units 1 and 2 3.3.1-17*Amendment 231/212
-NUCLEAR DESIGN INFORMATION
PORTAL-Spent Fuel Pool Storage 3.7.18 4.6 4.2 3.8 3.4 3 2.6 2.2 1.8//II'V//V//V I Acceptable
Conditionally
Acceptable
/"///V V I Unacceptable
I I/V V////o 1.4 5000 10000 15000 45000 40000 30000 35000 S'I-l 25000 Q,=E:::l ID20000 8:..:::l 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
-NUCLEAR DESIGN INFORMATION
PORTAL-Inverters-operating
3.8.7 3.8 ELECTRICAL
POWER SYSTEMS 3.8.7 Inverters-Operating
LCO 3.8.7 The Train H and Train J inverters shall be OPERABLE.------------
NOTE-----------
One inverter may be disconnected
from its associated
DC bus for24 hours 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 I, 2, 3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION
TIME A.One inverter A.l---------NOTE--------
Enter applicable
Conditions
and Required Actions of LCO 3.8.9,"Distribution
Systems-operating" with any vital bus de-energized.
Restore inverter to 7 days OPERABLE status.B.Required Action and B.l 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
-NUCLEAR DESIGN INFORMATIONInverters-operating
3.8.7 SURVEILLANCE
REQUIREMENTS
SR 3.8.7.1 SURVEILLANCE
Verify correct inverter voltage and alignment to required AC vital buses.FREQUENCY 7 days North Anna Units 1 and 2 3.8.7-2 Amendments
231/212
-NUCLEAR DESIGN INFORMATION
PORTAL-Distribution
Systems-Operating
3.8.9 3.8 ELECTRICAL
POWER SYSTEMS 3.8.9 Distribution
Systems-operating
LCD 3.8.9 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 LCO 3.8.g.a AC electrical
power distribution
subsystem(s)
North Anna Units 1 and 2 A.l REQUIRED ACTION---------NOTE--------
Enter applicable
Condit ions and Required Actions of LCO 3.8.4."DC Sources-Operating.
II for DC train(s)made inoperable
by inoperable
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 /> 16 hours from discovery of fail ure to meet LCO Amendments
231/212
ACTIONS-NUCLEAR DESIGN INFORMATION
PORTAL-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 /> LCO 3.8.9.a DC 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 inoperable.
discovery of fa;1 ure 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 LCO 3.8.9.b AC electrical
power distribution
subsystem(s)
E,--------NOTE----------
E,1 Declare associated
Immediately
Separate Condition shared component(s)
entry is allowed for inoperable.
each DC subsystem.
One or more required LCO 3.8.9.b DC electrical
power distribution
subsystem(s)
North Anna Units 1 and 2 3.8.9-2 Amendments
231/212
-NUCLEAR DESIGN INFORMATION
PORTAL-Distribution
Systems-operating
3.8.9 ACTIONS CONDITION REQU I RED ACTI ON 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
that result in a loss of safety function.SURVEILLANCE
REQUIREMENTS
\SR 3.8.9.1 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
EOUATIONS AND CONVERSIONS
HANDOUT SHEET EOUATIONS Q= Q=*.3 Q oc m Nal eireT oc
eire Ketf=1/(1-p)p=(Ketf-1)/Ketf SUR=26.06h 13 eff-p't=---A.eff p t=1 x 10-4 sec A.etf=0.1 sec*1 (for small positive p)22 DRW oc q>ti/q>avg
p=P lO S UR(I)°P=P e(l/t)°CRsm=S/(I-Kef!.)CRI(I-Kem)=CR 2 (1-Keffl)IIM=CR/CR x F=PA ril=pAy VI- Pump-E=IR Thermal Efficiency
=Net Work Out/Energy
In
+(y/_Y,2)
gc 2g c gc=32.2 Ibm-ft/lbf-sec
2 CONVERSIONS
1 Mw=3.41 X 10 6 Btu/hr 1 Curie=3.7 x 10 10 dps 1 hp=2.54 x 10 3 Btu/hr 1 kg=2.21 Ibm I Btu=778 ft-Ibf 1 gal watcr=8.35 Ibm°C=(5/9)(OF-32)1 ft3 waler=7.48 gal of=(915)(°C)+32-3-