ML082381167: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 14: | Line 14: | ||
| page count = 151 | | page count = 151 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000338/2008301]] | ||
=Text= | =Text= |
Revision as of 08:46, 12 July 2019
ML082381167 | |
Person / Time | |
---|---|
Site: | North Anna |
Issue date: | 08/21/2008 |
From: | NRC/RGN-II |
To: | |
References | |
ER-08-301 | |
Download: ML082381167 (151) | |
See also: IR 05000338/2008301
Text
Draft Submittal (Pink Paper)Reactor Operator Written Exam\NORTH ANNA JUNE 2008 EXAM 05000338/2008301
&05000339/2008301
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 1.001 G2.4.31 071INEW/IHIGHERI/ROINORTH
ANNAl6/20081
Given the following:
- During a Unit 1 load reduction for 1-PT-34.3, Turbine Valve Freedom Test, the following alarm is received:*1A-01, 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 the effect on the unit, and the action that will be taken to match Tave to Tref?A.All rod motion is inhibited;
adjust Turbine load ONLY to match Tave to Tref.B!" All rod motion is inhibited;
adjust Turbine load or adjust RCS boron concentration
to match Tave to Tref.C.Rod motion is allowed in'Bank Select';adjust Turbine load ONLY to match Tave to Tref.O.Rod motion is allowed in'Bank Select';adjust Turbine load, adjust RCS boron concentration, or use rods in Bank Select to match Tave to Tref.A Incorrect.
Change in RCS Cb is also allowable lAW the alarm response.Plausible because the applicant may believe that chern shim is not advisable while rods are frozen, and that changing turbine would be better course of action.B Correct.A Logic Cabinet failure freezes all rod motion, and before attempting
to move rods, the problem must be corrected.
C Incorrect.
Second half of choice plausibility
same as option A, and also an urgent failure in a Power Cabinet would allow the unaffected
groups to be moved in Bank Select, therefore choosing either C or 0 for this reason is credible.o Incorrect same reasons as C, but second half of option is correct action, with the exception of using rods.Plausibility
is enhanced for this choice because the alarm response allows use of rods in'bank select'if a power cabinet failure has occurred.Monday, June 30,20083:34:29
PM 1
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Emergency Procedures
/Plan: Knowledge of annunciator
alarms, indications,orresponse
procedures.
Question Number: Tier: Group: 2 2 Importance
Rating: 4.2 Technical Reference:
1 A-D1, Rod Control LP section 9.2 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 6518 Question History: 10 CFR Part 55 Content: 41.7,10 Scramble Range:A-D NORTH ANNA aI2 3456789 BCDBACDBAC
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Version: Answer: 1.00 NEW IDGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item directly evaluates the knowledge required by the selected topic because it requires knowledge of both the effect of the annunciator, and the action contained in the alarm response procedure MCS Time: I Points: Monday, June 30, 2008 3:34:30 PM 2
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 2.003 A4.07 OOIIBANKlROBINSON
2004IHIGHERJIRO/NORTH
ANNN6/2008/
Given the following:
- Unit 1 cooldown is in progress for refueling.
- RCS temperature
is 175 degrees F.*RCS pressure is 360 psig..*VCT pressure is 30 psig.*Seal Injection flows are 8 GPM to each RCP.The following alarm is received:*1C-G8, RCP 1A-B-C SEAL LEAK LO FLOW.*1C RCP se.al leakoffflowindicates
0.8 gpm andslowlydecreasing.
- 1C RCP Standpipe alarms are CLEAR.*1C RCP#1 Seal Leakoff temperature
is 180 degrees F and rising at 1 degree F every 10 minutes.Which ONE (1)of the following actions will be performed?
A'!OPEN 1-CH-HCV-1307, RCP Seal Bypass Isolation Valve, to increase sealleakoff
flow.B.Raise RCS pressure to high in the allowable band to increase sealleakoff
flow.C.Trip operating RCPs and isolate sealleakoff
due to insufficient
seal DP.D.Isolate#1 sealleakoff
for1C RCP to establish a pressure boundary at#2 seal.A Correct.Opening the seal bypass valve under low pressure conditions
will raise the seal leakoff flow in accordance
with the ARP.B Incorrect.
Raising RCS pressure would increase seal DP, and may increase seal leakoff flow, but is not directed by the ARP.Further the LTOP limit at this temperature
per Tech Specs is 375#which will have a negligible
effect on leakoff.The candidate who does not recognize this may choose this distractor.
Plausible because if pressure could beraiseda significant
amount it would have the desired effect.C Incorrect.
DP is 330 psig, sufficient
for continued RCP operation.
Minimum DP for ensuring desired seal leakoff flow as given by the AR is 275 psi.Plausible because pressure is low.o Incorrect.
Isolating sealleakoff
will decrease the#1 seal DP, placing a pressure boundary at#2 seal.This would be performed for a seal failure.This condition is expected for low pressure, and is not representative
of a seal failure.Plausible because at higher pressures, these indications
would lead to seal isolation.
Monday.June 30,20083:34:30
PM 3
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to manually operate and/or monitor in the control room: Rep seal bypass Question Number:2 Group: 1 Importance
Rating: 2.6 Reference(s)
-ARP 1 C-G8, 1-0P-5.2 Proposed References
to be provided to applicants
during examination
-None Learning Objective-U 3493 Question History-10 CFR Part 55 Content-41.7/10 Comments-KA Match: Item evaluated knowledge of when and under what conditions
seal bypass may be used.NORTH ANNA BANK IDGHER RO 612008 Source: Cognitive Level: Job Position: Date: This item was taken from a Robinson item from 2004.Stem was changed to ensure plant specific information, two options were changed for plausibility.
MCS Time: 1 Points: 1.00 Version:0123456789
Answer: A BAD CDC ABC Scramble Range: A-D Source If Bank: ROBINSON 2004 Difficulty
Level: Plant: Previous NRC?: Monday, June 30,20083:34:30
PM 4
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 1508 RO ONLY 3.004 G2.2.3 003INEW//LOWERlIROINORTH
ANNAl61200SINO
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.
A Correct.Lineup is correct for normal arangement
of system (no equipment OOS)and ensures BIT concentration
and BIT remains full.B Incorrect.
A BAST is normally aligned to Unit 1;lineup thru BIT is correct.C Incorrect.
This lineup ONLY recircs the specified BAST and as noted above would not be normal since it fails to include the BIT.o Incorrect.
In this case again the B BAST would only be used if the C BAST were unavailable;
the BIT lineup portion is correct.All distractors
are plausible since several lineups are possible for various evolutions.
The"normal" lineup is based on a configuration
that maintains TRMrequirementsfor
funtional sources and flowpaths.
The normal on service tank and associated
recirc path is different between the Units.Monday, June 30, 2008 3:34:30 PM 5
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 004 Chemical and Volume Control System 2.2.3 (multi-unit
license)Knowledge of the design, procedural, and operational
differences
between units.Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.8 OP-8 series procedures
Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: CFR: 41.5/41.6/41.7/41.10/45.12
Comments: MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW LOWER RO 6/2008 1.00 Version:0I23456789
Answer:AAAAAAAAAA
Items Not Scrambled Source If Banle Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO Monday, June 30, 2008 3:34:30 PM 6
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 4.005 KI.06 04IIMODIFIED/IHIGHERlIROINORTH
ANNAJ61200S1
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 required, and the reason for the minimum flow, in accordance
with 1-0P-14.1, Residual Heat Removal.A.2500 GPM;satisfies Technical Specification
minimum flow requirements
in Mode 6.2500 GPM;prevents flow induced chatter on Sl Accumulator
check valves.C.3000 GPM;satisfies Technical Specification
minimum flow requirements
in Mode 6.D.3000 GPM;prevents flow induced chatter on SI Accumulator
check valves.A Incorrect.
Plausible because minimum RHR operability
requirements
are based on cavity level.B Correct.Flow induced chatter can damage SI Accumulator
check valves, because RHR discharge uses a portion of Sl Accumulator
discharge piping.C Incorrect.
3000 GPM would be the minimum flow requirement
if cavity level was higher than 23 feet or if RCS temperature
was greater than 140 degrees F, and the precaution
is used to satisfy TS.D Incorrect.
Plausible because reason is correct, but flow is incorrect.
Monday, June 30, 2008 3:34:30 PM 7
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the physical connections
and/or cause-effect
relationships
between the RHRS and the following systems: ECCS Question Number: Tier: Group: 2 1 Importance
Rating: 3.5 Technical Reference:
1-0P-14.1 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 10457, U 444 Question History: 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA MODIFIED HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates cause-effect
relationship
between RHR and SI systems because it tests RHR flow requirement
to prevent damage to SI components
MCS Time: I Points: 1.00 Version: aI23456789 Answer: BADADCAADD
Source If Bank: Difficulty
Level: Plant:
Previous NRC?: Monday, June 30,20083:34:30
PM 8
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 5.006 K2.02 043INEW/IHIGHERlIROINORTH
ANNAl6/2oo8INO
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 itls breaker position for the current plant conditions?
480 Volt MCC...A'!I 1 H1;breaker is open.B.1 H1;breaker is closed.C.1J1;breaker is open.D.1J1;breaker is closed.A Correct.Correct power supply, and breaker is normally open;during RCS cool down in Mode 3, breaker is closed below 1990 psig until the valve is closed below 950 psig.Once in Mode 4 below 350 degrees, power is again removed from the valve.B Incorrect.
See A above.Breaker would be opened below 950 psig after valve is closed.C Incorrect.
Wrong power supply, but plausible supply.(Supplies MOV-1865C for 1C SI Accumulator)
Breaker is normally open, and is open in this condition.
D Incorrect.
Wrong power supply, incorrect breaker position, but breaker would be closed throughout
most of the cooldown.It is opened below 950 psig.See description
of A and C above for detail.Monday, June 30, 2008 3:34:30 PM 9
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of bus power supplies to the following:
Valve operators for accumulators
Question Number: Tier: Group: 2 1 Importance
Rating: 2.5 Technical Reference:
NCRODP-52, Table 3;51 LP;1-0P-3.3, step 5.8 1-0P-26A Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 3887 Question History: 10 CFR Part 55 Content: 41.5 Scramble Range:A-D NEW IDGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Topic asks power supply to Accumulator
Valve Actuators;
test item evaluates knowledge of the MOVs and their operation MCS Time: I Points: 1.00 Version:0I23456789
Answer: ABADDAC CDD Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO Monday, June 30, 2008 3:34:30 PM 10
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 6.007 A4.10 046IMODIFIED//LOWERlIROINORTH
ANNN6/20081
Given the following:
- Unit 1 is in Mode 3.*PRT level is 74%and INCREASING
SLOWLY.*PRT pressure is 14 psig and INCREASING
SLOWLY.*PRT temperature
is 155°F and INCREASING
SLOWLY.Which ONE of the below is the cause of the conditions
above, and the indications
that may be used to diagnose the cause?A.Seat leakage from a Pressurizer
Safety valve;Temperature
indicator ONLY on the Safety Valve Tailpipe.Seat leakage from a Pressurizer
Safety valve;Temperature
indicator and acoustical
monitor on the Safety Valve Tailpipe.C.Seat Leakage from a Pressurizer
PORV;Temperature
indicator and acoustical
monitor on the Relief Valve Tailpipe.D.Seat Leakage from a Pressurizer
PORV;Acoustical
monitor ONLY on the Relief Valve Tailpipe.A Incorrect.
The safety valve has acoustic monitor indication
and temperature
indication, but plausible because there are multiple temperature
indications
on the Verical Board.B Correct.The safety valve has 2 acoustic monitors and 1 temperature
indication
C Incorrect.
Plausible because of same reason as A, except that PORVs have open/closed
indicators, and are not provided with acoustic monitors.D Incorrect same as C, except that if an applicant believes a PORV is leaking, these are the indications
available for a safety valve, so it can be confusing.
Monday, June 30, 2008 3:34:30 PM 11
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to manually operate and/or monitor in the control room: Recognition
of leaking PORV/code safety Question Number: Tier: Group: 2 1 Importance
Rating: 3.6 Technical Reference:
Response Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 15844 Question History: 10 CFR Part 55 Content: 41.7 Scramble Range:A-D NORTH ANNA MODIFIED LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates recognition
and determination
of which valve is leaking into the PRT.MCS Time: 1 Points: 1.00 Version:0I23456789
Answer:BB CBAACCAA Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:31 PM 12
QUESTIONS REPORT fo'r NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 7.007 K3.01 047lNEW/fHIGHERJIROINORTH
ANNAl6120081NO*A calibration
error during the refueling outage results in the PRT level transmitter
reading 20%lower than actual level.*The Unit is now at 100%power and PRT level indication
is 72%.Which ONE of the following describes the affect the calibration
error will have assuming multiple PORV lifts occur during recovery from a spurious 81 in which one train failed to reset?A.More volume will be available in the PRT to accommodate
the PORV discharge so it will take more time for the PRT rupture disk to rupture.B.More volume will be available to accommodate
the PORV discharge but this will not affect the time it takes for the PRT rupture disk to rupture.Less volume will be available in the PRT to accommodate
the PORV discharge so it will take less time for the PRT rupture disk to rupture.D.Less volume will be available in the PRT to accommodate
the PORV discharge but this will not affect the time it takes for the PRT rupturediskto rupture.A Incorrect.
Plausible since historically
the effect of actual vs.indicated is often confused, if candidate assumes more volume available this will tend to imply longer time to reach setting (100#)dip so this distractor
is plausible.
B Incorrect.
As noted above operators maintain level based on their indication;
for the condition given maintaining
the PRT at a typical indicated level of 72%means it is actually 92%full, 2nd part is plausible since rupture disc is a function of pressure, candidate may not connect that volume differences
in PRT will affect how fast pressure rises.C Correct.As noted above in actuality the PRT is almost completely
full (horizontal
cylindrical
tank)as such for the conditions
provided (PRT actually above normal operating range and PORVs discharging)
the PRT will rupture much sooner than would be expected.D Incorrect.
As stated above the amount and given time for pressure rise is somewhat dependent on initial volume, again the candidate may not equate this to the rupture disc rupturing sooner since the 100#dip setpoint does not change with respect to the calibration
error discussed.
Monday, June 30, 2008 3:34:31 PM 13
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Pressurizer
Relief Tank/Quench
Tank System (PRTS)Knowledge of the effect that a loss or malfunction
of the PRTS will have on the following:
Containment
Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.3 RCS LP, AR, GFES Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10CFRPart 55 Content: Comments: 41.7/45.6 MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 6/2008 1.00 Version:0I23456789
Answer:CCCCCCCCCC
Items Not Scrambled Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO Monday, June 30, 2008 3:34:31 PM 14
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 8.008 AA2.24 002INEW//lllGHERlfROINORTH
ANNA/6/2008/
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;1010 psig.B.Condenser Steam Dumps;1050 psig.C.SG PORVs;1010 psig.D.SG PORVs;1050 psig.A Correct.Main Steam pressure of approximately
1020 psia (1005 psig)corresponds
to 547 degrees F, 1010 is close based on readability
of meters.No MSU, so condenser remains available.
B Incorrect.
Steam pressure is plausible because it is the pressure thatSG PORVs will operate at to maintain 551 degrees F if Condenser dumps are not available.
C Incorrect.
Since no MSU, SG PORVs do not have to control pressure.Plausible because containment
pressure is close to setpoint for MSU, and pressure is correct for actual control point of 547 degrees.D Incorrect same as C but if SG PORVs were controlling, then this would be the pressure.Monday, June 30, 2008 3:34:31 PM 15
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to determine and interpret the following as they apply to the Pressurizer
Vapor Space Accident: Value at which turbine bypass valve maintains header pressure after a reactor trip Question Number: Tier: Group: 1 1 Importance
Rating: 2.6 Technical Reference:
E-O, pages 6-10 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 12458, U 12463 Question History: 10 CFR Part 55 Content: 41.5,41.10
Comments: KA Match: Item evaluates steam pressure maintained
during a steam space LOCA, based on whether MSLI has actuated and which Tave would be maintained.
Scramble Range:A-D NORTH ANNA 0123456789
ADCDCABBCA
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Version: Answer: 1.00 Points: NEW HIGHER RO 612008 Source: Cognitive Level: Job Position: Date: Have developed similar items in the past evaluating
steam dumps or PORVs, but not in this context MCS Time: Monday, June 30, 2008 3:34:31 PM 16
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 9.008 K4.01 047INEW/ILOWERlIROINORTH
ANNAJ6120081
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.*1H EDG operates as designed.Which ONE of the following describes the operation of CC Pumps for this event?A.CC Pump1B starts when Bus1H is deenergized;
CC Pump1A starts as soon as Bus1H is reenergized.
Bl'" CC Pump1B starts when Bus1H is deenergized;
CC Pump1A restarts 15 to 20 seconds after Bus1H is reenergized.
C.CC Pump1B starts 15 to 20 seconds after Bus1H is reenergized;
CC Pump1A starts 15 to 20 seconds after Bus1H is reenergized.
D.CC Pump1B starts 15 to 20 seconds after Bus1H is reenergized;
CC Pump1A remains deenergized.
A Incorrect.
CC Pump1B does start when bus1H is deenergized
due to CC Pump1A Trip (Breaker disagreement)
but since Bus1H is deenergized, it requires 15 to 20 seconds of normal voltage to restart.B Correct.CC Pump1B starts when bus1H is deenergized
due to CC Pump1A Trip (Breaker disagreement), the associated
time delay is correct and is a design feature to ensure EDG is maintained
within voltage and frequency as loads are connected.
C Incorrect.
Plausible because Pump1B would operate this way if Bus 1 J feeder tripped.The time delay is associated
with the bus supplying the affected pump.D Incorrect.
Plausible as in C, and also that Pump 1A would not restart, since1B would already be running and1A would not be required.Monday, June 30, 2008 3:34:31 PM 17
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of CCWS design feature(s)
and/or interlock(s)
which provide for the following:
Automatic start of standby pump Question Number: Tier: Group: 2 1 Importance
Rating: 3.1 Technical Reference:
CCWLP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 3656 Question History: 10 CFR Part 55 Content: 41.7 Scramble Range:A-D NORTH ANNA NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: KA is matched because item tests knowledge ofautostart interlocks
for both standby pumps and pumps reenergized
from undervoltage
MCS Time: 1 Points: 1.00 Version:0123456789
Answer: BDAABABBBC Source If Banle Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:31 PM 18
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 10.009 G2.4.4 059IMODIFIED/IHIGHERlIROINORTH
ANNN6/20081
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 low.*Containment
Pressure-23 psia.*Containment
Radiation levels-Rising.*RWST level-32%and decreasing
at1%every 4 minutes.*RCS pressure-800 psig and decreasing
slowly.*Core Exit TCs-500 degrees F.*RVLlS Full Range indication
94%.Based on these indications, which ONE of the following procedure entry requirements
are met?A.1-FR-C.2, Response to Degraded Core Cooling Bl" 1-ES-1.2, Post-LOCA Cooldown and Depressurization
C.1-ES-1.3, Transfer to Cold Leg Recirculation
D.1-E-2, Faulted Steam Generator Isolation A-Incorrect.(see B)Subcooling
below minimum limit, plausible because RVLlS is less than 100%, but not low enough for entry to FR-C.2.B Correct.RCS Pressure is notstable,and
at1%per 3 minutes RWST reduction, it will be more than 30 minutes to reach entry conditions
for ES-1.3.C Incorrect.
RCS pressure and RWST level are high.Entry to ES-1.3 on low RWST level plausible because eventually, entry conditions
will be met.But they are met for ES-1.2 now.D Incorrect.
SG pressures are trending down, which leads one to believe they must be isolated in accordance
with E-2, but incorrect because the RCS is leading the cooldown, so SGs are not actully faulted, they are a heat source to the RCS.Monday, June 30, 2008 3:34:31 PM 19
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Emergency Procedures
/Plan: Ability to recognize abnormal indications
for system operating parameters
which are entry-level
conditions
for emergency and abnormal operating procedures.
Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 4.5 E-O, F-O Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: U 12203 WTSI Bank 41.10 Comments: KA Match: Item evaluates system operating parameters (RCS, ECCS)related to entry to EOPs, requiring the applicant to determine which entry requirements
are met.This item has been used before.Facility not identified, by nomenclature, it appears this item was last used on the Wolf Creek AUDIT exam in 2006.Modified several values in stem and changed option A MCS Time: Source: Cognitive Level: Job Position: Date: Points: MODIFIED HIGHER RO 6/2008 1.00 Version:0I23456789
Answer:BB DADDBBCB Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:31 PM 20
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 11.010 KS.OI 048INEW//lllGHERJIRO/NORTH
ANNN6/2008/
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.30 minutes;letdown flow will be manually increased to reduce Pressurizer
level.B.30 minutes;the letdown backpressure
control valve setpoint will be adjusted to ensure charging and letdown flows are approximately
equal while PZR pressure rises.Cr 60 minutes;letdown flow will be manually increased to reduce Pressurizer
level.D.60 minutes;the letdown backpressure
control valve setpoint will be adjusted to ensure charging and letdown flows are approximately
equal while PZR pressure rises.A Incorrect.
Plausible because maximum tech spec heatup rate is 200 degrees F per hour.Correct action for letdown flow (1-CH-PCV-1145
is in manual control).B Incorrect.
Plausible same reason as A.Incorrect action for letdown flow since 1-CH-PCV-1145
is in manual control and there must be a Charging/Ltdn
mismatch to drop level.C Correct.Admin limit of 90 o F/hr means it will take approximately
60 minutes to reach saturation
in the PZR.Correct action for letdown flow (1-CH-PCV-1145
is in manual control).D Incorrect.
Admin limit of 90 o F/hr means it will takeapproximately60
minutes to reach saturation
in the PZR so this part is Gorrect.Incorrect action for letdown flow since 1-CH-PCV-1145
is in manual control and there must be a Charging/Ltdn
mismatch to drop level.Monday, June 30, 2008 3:34:31 PM 21
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the operational
implications
of the following concepts as the apply to the PZR PCS: Determination
of condition of fluid in PZR, using steam tables Question Number: Tier: Group: 2 1 Importance
Rating: 3.5 Technical Reference:
1-0P-1.1, Steam Tables Proposed references
to be provided to applicants
during examination:
Steam Tables Learning Objective:
Question History: 10 CFR Part 55 Content: 41.10 Comments: KA Match: Item evaluates subcooling
by asking how long it will take to reach saturation
conditions
at a specified heatup rate that must be knownbythe applicant.
Scramble Range:A-D NORTH ANNA NEW HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: New item;have developed similar, but always have given actual heatup rate instead of asking limit.Also, this facility draws a bubble in a different manner MCS Time: I Points: 1.00 Version:0123456789
Answer: CCDCDBDC BA Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:31 PM 22
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 12.011 EK2.02 004fNEW//LOWERlIRO/NORTH
ANNA/6/2008/
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%.Which ONE of the following describes the ECCS pump alignment when the initial swapover to Cold Leg Recirculation
is performed?Low Head SI Pump suction from Containment
Sump;Charging Pump suction from LHSI Pumps.B.Low Head SI Pump discharge to RCS cold legs;Charging Pump suction from Containment
Sump.C.Low Head SI Pump suction from Containment
Sump;Charging Pump suction from RWST.D.Low Head SI Pump discharge to RCS Cold Legs;Charging Pump suction from RWST.A Correct.LHSI Pumps automatically
swap to Containment
Sump at 16%RWST level.Alignment prior to returning to E-1 is to align LHSI to charging pump suction and to close RWST suction valves for Charging Pumps.B Incorrect.
Plausible because ECCS does discharge to cold legs, and some LHSI flow will go to cold legs, some will go to Charging, but Charging pumps are not aligned to the sump.Plausible because LHSI does take suction from the sump.C Incorrect.
Plausible because suction source is correct, and also that charging is a low volume injection, so the last step is to isolate Charging from the RWST, The applicant may assume that the charging pumps are not realigned until the RWST reaches 8%, as indicated by a caution in the procedure.
D.Incorrect.
See explanations
above.Monday, June 30, 2008 3:34:31 PM 23
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 1508 RO ONLY Knowledge of the interrelations
between the Large Break LOCA and the following:
Pumps Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 2.6 ES-1.3, through step 8 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 3412 10 CFR Part 55 Content: 41.10 Comments: KA Match: Item evaluates operation of Charging and Low Head SI pumps following a Large Break LOCA when swap to Cold Leg Recirculation
is required.Therefore, the relationship
between the major pumps providing RCS makeup during a LOCA MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW LOWER RO 6/2008 1.00 Version:0123456789
Answer:ACBCB CADAA Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:31 PM 24
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 041508 RO ONLY 13.012 K6.04 050IMODIFIED//HIGHERI/ROINORTH
ANNAl6120081
Given the following:*A plant load reduction is in progress.*Turbine First Stage Pressure Channel, 1-MS-PT-1446, sticks at a pressure equivalent
to 50%power.*Reactor power is currently 8%.Which ONE of the following describes the RPS permissive
affected, and the resulting effect on the unit?A.P-7 cannot be satisfied;
the reactor would trip on loss of 1 RCP.B.P-8 cannot be satisfied;
the reactor would trip on loss of 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 2 RCPs.A Incorrect.
The first part is true, P-7 cannot be satisfied in the current plant condition, because one impulse pressure channel is stuck above 10%.This means that P-13 cannot be satisfied.
P-7 requires input from P-13 and P-10.The second part is incorrect but plausible because P-8 inputs the loss of flow trip on 2 RCPs.B Incorrect.
Plausible because the impulse channel is stuck at a value higher than the P-8 power value.P-8 is input by power range instrumentation.
Also plausible because if the first half was true, the second half would also be true, because P-8 is the permissive
for the loss of flow trip-1 RCP.C Correct.P-7 cannot be satisfied because P-13 must be active (2/2 impulse pressures<10%)for P-7 to be active.P-10 is active because 3/4 PR Nls are below 10%, but only solves half of the input for P-7 to be active.o Incorrect.
As described above P-8 is a function of NIS only.Low flow trip combintation
is incorrect, but could be chosen based purely on logic that with power between 10%and 30%is the range for 2/3 10 flow trip.Monday, June 30, 2008 3:34:32 PM 25
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the effect of a loss or malfunction
of the following will have on the RPS: Bypass/Block
circuits Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.3 RPS LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 16382 10 CFR Part 55 Content: 41.7 Comments: KA Match: Item evaluates effect of a loss of P-7, Low Flow Reactor Trip block permissive, for a plant condition that would require the that trip to be blocked.Modified itempreviouslydeveloped
by NRC;changed power level, and significantly
changed distractors.
MCS Time: Source: Cognitive Level: Job Position: Date: Points: MODIFIED HIGHER RO 612008 l.OO Version:0I23456789
Answer:CCDD DCA A DC Scramble Range:A-D Source If Banle Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:32 PM 26
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 14.013 AI.07 014INEW//HIGHER//ROINORTH
ANNA/612008/
An event has occurred on Unit 1 resulting in core damage.Containment
pressure peaked at 28 psia and is now 16 psia and slowly trending down.Containment
radiation peaked at 2E+5R/hr and is now 1 E+4R/hr and slowly trending down.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.The BOP recommends
reducing AFW to 50 gpm to each SG to minimize RCS cooldown.Which ONE of the following describes how the crew should respond to the BOPs recommendation
and the Basis for their decision?A.AFW may be reduced to 50 gpm to each SG since Adverse Containment
Criteria were cleared as Containment
pressure decreased to the current value.B.AFW may be reduced to 50 gpm to each SG since Adverse Containment
Criteria were cleared as Containment
radiation decreased to the current value.C.AFW must be maintained>
340 gpm total since Adverse Containment
Criteria are still in effect because of the Containment
pressure transient.AFW must be maintained>
340 gpm total since Adverse Containment
Criteria are still in effect because of the Containment
radiation transient.
Monday, June 30, 2008 3:34:32 PM 27
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY A Incorrect.
Since CNTMT rad level exceeded 1 E+5R1hr adverse numbers are still required to be used;adverse criteria cannot be cleared when rad levels exceed 1 E+5R1hr without an engineering
evaluation.
Would be correct if not for the requirement
to use adverse values.B Incorrect.
As noted above Adverse Containment
criteria cannot be exited without an Engineering
Evaluation.
C Incorrect.
First part of the distractor
is true, however the reasonadversecriteria
is required to be used is rad level going above 1 E+5R1hr, NOT pressure.D Correct.Because of the radiation transient adverse criteria cannot be exited so the procedural
requirement
is to maintain 340 gpm total AFW flow.013 Engineered
Safety Features Actuation System (ESFAS)A 1.07 Ability to predict and/ormonitorchanges
in parameters (to Prevent exceeding design limits)associated
with operating the ESFAS controls including:
Containment
radiation Question Number: Tier: Group: 2 1 Importance
Rating: 3.6 Technical Reference:
E-O and ERG Background
document Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: 43.5 Comments: Items Not Scrambled NORTH ANNA NEW HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Elevated containment
radiation results in invoking of adverse CNTMT criteria;these criteria are needed to ensure certain safety functions are met/maintained
based on the assumed impact on accident monitoring
instrumentation.
the operator must understand
and correctly apply these crieria in order to correctly operate this portion of ESFAS (AFW).MCS Time: I Points: 1.00 Version:0I23456789
Answer: DDDDDDDDDD
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:32 PM 28
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 15.013 K4.15 OOIINEW//LOWERlIROINORTHANNAl6/2008INO
The Unit is at 100%power.Assume 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;indicating
lights in Train A ONLY must be used to determine the affected Train.B.Train specific Safeguards
Trouble annunciators
are provided in the control room;indicating
lights in Train A ONLY must be used to determine the affected Train.C.A common Safeguards
Trouble annunciator
is provided in the control room;indicating
lights in Train A or Train B can be used to verify the affected Train.Dr Train specific Safeguards
Trouble annunciators
are provided in the control room;indicating
lights in Train A or Train B can be used to verify the affected Train.A Incorrrect.
Plausible because many alarms have multiple inputs and the candidate who is unfamiliar
with the system is likely to default to the common alarm, similarly the candidate may assume that one can only identify a general warning condition in the affected train (this is NOT the case)and infer that train A is affected since this distractor
directs looking in one train to identify the condition.
B Incorrrect.
First part is true train specific alarms are provided, as stated above the candidate may assume that one can only identify a general warning condition in the affected train (this is NOT the case)and infer that train A is affected since this distractor
directs looking in one train to identify the condition.
C Incorrrect.
Plausible because many alarms have multiple input and the candidate who is unfamiliar
with the system is likely to default to the common alarm, 2nd part is correct, as part of the design feature of the system status light in each train show the status of both trains, although primarily intended as a means of monitoring
status during surveillance
testing they will provided the same information
for the conditions
given in the stem.D Correct.The*trouble
alarm will alert the operator to the problem, looking in either rack will allow the operator to determine that the trouble annunciator
is due to a general warning and using the amber and green lights provided, verify which train is affected and verify that the opposite train is unaffected.
Monday, June 30, 2008 3:34:32 PM 29
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 013 Engineered
Safety Features Actuation System (ESFAS)Knowledge of ESFAS design feature(s)
and/or interlock(s)
which provide for the following:
Continuous
testing Question Number: Tier: Group: 2 1 Importance
Rating: 2.6 Technical Reference:
AR, RPS Lesson Plan Proposed references
to be provided to applicants
during examination:
None Learning Objective:
8958 Question History: 10 CFR Part 55 Content: 41.7 Comments: Items Not Scrambled NORTH ANNA NO a12 3456789 DDDDDDDDDD
Source If Bank: Difficulty
Level: Plant: Previous NRC?: NEW LOWER RO 612008 Source: Cognitive Level: Job Position: Date: NAPS does not have a continuous
testing feature that is found in some plant designs.Per discussion
w/USNRC R-II, this meets the intent of the KA in that it tests the operators knowledge of how the system is designed to alert the operator to an abnormal condition within a train and how the affected train can be verified (verification
of status of both trains relative to a general warning condition)
MCS Time: 1 Points: 1.00 Version: Answer: Monday, June 30, 2008 3:34:32 PM 30
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 16.015 AKl.07 005IBANKlIHIGHERlIROINORTH
ANNN6/20081
Given the following:
- Unit 1 is at 100%power.*The following alarm is received:*1C-G7, RCP 1A-B-C SEAL LEAK HI FLOW*RCP1B Seal Leakoff flow is 5.9 GPM and slowly rising.*RCP1B No.1 Seal DP indicates 220 psid and lowering slowly.*Annunciator
1C-G2, RCP 1B STANDPIPE HI LEVEL is NOT LIT.*Seal leakoff has lowered on RCP1A and 1 C.*Seal Return temperature
is rising slowly.Which ONE of the following describes the event in progress and the action required?A'!RCP#1 seal failure;trip the reactor, trip the RCP, and isolate sealleakoff
within 5 minutes.B.RCP#1 seal degraded;monitor RCP bearing temperatures
and initiate a plant shutdown to Hot Standby.C.RCP#2 seal failure;trip the reactor, trip the RCP, and isolate sealleakoff
within 5 minutes.D.RCP#2 seal degraded;monitor RCP bearing temperatures
and initiate a plant shutdown to Hot Standby.A Correct.If the seal is not holding, leakoff will rise, and DP will go toward O.If#1 seal has failed in this way, then a reactor trip is required.B Incorrect.
Plausible because this action would be taken for a seal failure where leakoff flow was low<<.8 gpm).C Incorrect.
- 2 Seal failure is indicated by a standpipe high level alarm.In this case, the alarm is not lit.Plausibility
is maintained
because the applicant must determine failure based on conditions, and also because the standpipe can be associated
with#3 seal.D Incorrect.
As noted above degradation
of#2 seal will cause decreased#1 seal leakoff, however indications
provided are indicative
of athe more severe condition of failure of the#1 seal.Candidate may choose this if they are unfamiliar
with seal failure diagnostics.
Monday, June 30, 2008 3:34:32 PM 31
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the interrelations
between the Reactor Coolant Pump Malfunctions (Loss of RC Flow)and the following:
RCP seals Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 2.9 1-AP-33.1 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 11101 10 CFR Part 55 Content: 41.10 Comments: KA Match: The item evaluates an RCP malfunction
by evaluating
an RCP seal failure, demonstrating
that the topic related to knowledge of interrelations
between RCP Malfunctions
and RCP seals is met.This item was developed without use of the bank but there are very similar bank items available MCS Time: Source: Cognitive Level: Job Position: Date: Points: BANK HIGHER RO 6/2008 1.00 Version:0I23456789
Answer:ACBB DCDDCC Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:32 PM 32
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 17.016 Kl.02 072INEW//HIGHERlIROINORTH
ANNA/6/2008/
Given the following:
- Unit 1 is operating at 50%power.*All Control systems are in automatic.
- Loop1B Tcold RTD fails low.Which ONE of the following describes the response of the Pressurizer
Level Control System and Rod Control System?A.Charging flow decreases;
Control rods step OUT.B.Charging flow decreases;
Control rods do not move.C.Charging flow remains constant;Control rods step OUT.Charging flow remains constant;Control rods do not move.A Incorrect.
Applicant may misunderstand
and assume the failure affects the control circuit (not selected out by Median Signal Selector)since pzr Ivl program and rod control program are both a funtion of temperature
it is reasonable
to assume both would respond.B Incorrect.
Plausible as in A, but also takes into account the existence of OPdT and OTdT rod stops, although logic is 2/3 the candidate may confuse woth the over power rod stop which only requires a single channel, in that case it would be plausible for PZR level program to be affected but rods to remain stationary.
C Incorrect.
Plausible if candidate assumes that PZR level control sip is function of a different process input (e.g.1 st stage pressure, N-44 power, etc..).D Correct.The failure affects the subject protection
channel but is selected out as a function of the Median Signal Selector.Monday, June 3D, 2008 3:34:32 PM 33
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the physical connections
and/or cause-effect
relationships
between the NNIS and the following systems: PZR LCS Question Number: Tier: Group: 2 2 Importance
Rating: 3.4 Technical Reference:
PZR Press/Lvi Ctrl LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 10654 Question History: 10 CFR Part 55 Content: 41.7 Scramble Range:A-D NORTH ANNA NEW HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates NNIS (RTD)failure for input to PZR level control MCS Time: 1 Points: 1.00 Version:0123456789
Answer: DADADAB C DA Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30,20083:34:32
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 18.017 A4.02 074IMODIFIED/IlDGHERlIRO/NORTH
ANNN6120081
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 psia and is now slowly trending down.*Core Exit T/Cs are 545 degrees F.Which ONE of the following describes the requirement
for operation of RCPs in the present condition, and the reason why?A.RCPs should remain running because ECCS flow is inadequate
to ensure adequate core cooling.8.RCPs should remain running because forced circulation
provides sufficient
core cooling until RCP trip criteria is met.RCPs should be stopped because an inadequate
core cooling condition could develop if RCPs were tripped or lost later in the event.O.RCPs should be stopped to prevent damage to the RCPs due to loss of cooling water.A Incorrect.
One Charging pump is running.Only 1 charging pump is required to be running to allow for RCP trip.Plausible because all other ECCS flow is lost and applicant could believe that both must be running.Also, applicant may miss adverse containment
and believe they should be running because RCS subcooling
is adequate 8 Incorrect.
Statement is true if RCPs should remain running, but subcooling
is below 85 degrees F, and they should be tripped because containment
is>20 psia C Correct.ERG executive volume contains RCP trip/restart
discussion, and concern is that if they are allowed to remain running under certain S8LOCA scenarios, and they are tripped later in the event, the core could uncover.o Incorrect.
Containment
pressure was never high enough for COA that would cause the loss of cooling water.(28 PSIA).Plausible because other ESFAS actuations
have ocurred and the applicant may misunderstand
that CC isn't lost until after COA.Monday, June 30, 20083:34:32
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to manually operate and/or monitor in the control room: Temperature
values used to determine RCS/RCP operation during inadequate
core cooling (i.e., if applicable, average of five highest values)Question Number: Tier: Group: 2 2 Importance
Rating: 3.8 Technical Reference:
E-O Continuous
action page, ERG Exec Volume Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 12451 Question History: 10 CFR Part 55 Content: 41.10 Comments: KA Match: item evaluates RCP operation under a temperature-pressure
relationship
from indications
provided by the ICCM and other plant conditions.
The KA is met because RCP operation is being determined
based on margin to saturation.
Scramble Range:A-D NORTH ANNA MODIFIED IDGHER RO 612008 Source: Cognitive Level: Job Position: Date: A question evaluating
the exact wording of the KA would have been double jeopardy with Question 82.NRC directed to develop an item on this topic instead of allowing KA swap.MCS Time: 1 Points: 1.00 Version:0123456789
Answer: CADAB CBCAD Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:32 PM 36
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 19.022 A2.06 053INEW//lllGHERiIRO/NORTH
ANNA/6/2008/
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 describes the MINIMUM containment
temperature
requiring entry into a Technical Specification
action statement, and the action required?A.105 degrees F;ensure steam chiller running or align Service Water to Containment
Air Recirc Fans.B.105 degrees F;ensure Containment
Air Recirc Fans are running with backdraft dampers closed.115 degrees F;ensure steam chiller running or align Service Water to Containment
Air Recirc Fans.D.115 degrees F;ensure Containment
Air RecircFansare running with backdraft dampers closed.A Incorrect.
Temperature
is incorrect but plausible because the procedure designates
105 degrees F as the minimum temperature.
8 Incorrect.
Same as A, and also the action may be performed later but backdraft dampers must be checked open.Plausible because it is reasonable
to believe that a backdraft damper should be closed to prevent short-cycling
of air.C Correct.TS LCO is 115 degrees F is correct.Procedure provides option of Steam Chiller or Sevice Water to provide Containment
cooling for the case where the Mechanical
Chiller is unavailable.
D Incorrect.
TS LCO is 115 degrees F is correct.Incorrect for same reason as second half of B.Monday, June 30, 2008 3:34:32 PM 37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY CNTMT Cooling: Ability to (a)predict the impacts of the following malfunctions
or operations
ontheCCS;and (b)based on those predictions, use procedures
to correct, control, or mitigate the consequences
of those malfunctions
or operations:
Loss of CCS pump Question Number: Tier: Group: 2 1 Importance
Rating: 2.8 Technical Reference:
1-AP-35, tech specs Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 1958 Question History: 10 CFR Part 55 Content: CFR: 41.5/43.5/45.3/45.13 Scramble Range: A-D NORTH ANNA NEW mGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates knowledge for the equivalent
of a CCS pump at North Anna;it tests knowledge of the effect and actions taken for trip of the Mechanical
Chiller, which provides normal containment
cooling for CAR Fans..MCS Time: 1 Points: 1.00 Version:0123456789
Answer: CDCBABACAC
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:33 PM 38
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 20.022 AK3.03 006INEW/tmGHERJ/ROINORTH
ANNA/6/2008/
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 describes restrictions
on the Excess Letdown Lineup, and the reason for the restrictions?
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;reactor power should be monitored because a dilution may occur due to lower boron concentrations
in the Excess Letdown piping.Flow through ONLY one loop drain to prevent the possibility
of bypassing 81 flow to the 2 intact loops in a design basis accident;reactor power should be monitored because a boration may occur due to higher boron concentrations
in the Excess Letdown piping.C.Excess Letdown Pressure must NOT exceed 75 psig to prevent overpressurizing
the VCT;reactor power should be monitored because a dilution may occur due to lower boron concentrations
in the Excess Letdown piping.D.Excess Letdown Pressure must NOT exceed 75 psig to prevent overpressurizing
the VCT;reactor power should be monitored because a boration may occur due to higher boron concentrations
in the Excess Letdown piping.Monday, June 30, 2008 3:34:33 PM 39
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY A Incorrect.
The first half is correct.The second half is incorrect but plausible because a reactivity
event may occur, and it is reasonable
to assume that it is a dilution similar to ion exchange beds being placed in service.B Correct.Basis for using ONLY one loop is correct.1-0P-8.5 cautions the operator about the potential for boration based on the likely condition that excess letdown will have likely last been used during the outage with boron concentration
much higher than current Cb.C Incorrect.
Excess Letdown is maintained
less than 150 psig.VCT pressure is maintained
less than 75 psig.If the pressure was correct, the first half of this option would be correct.As noted above the procedure addresses boration concern not dilution.o Incorrect.
Same as C regarding pressure concern, but the reactivity
caution is correct.Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: Performance
of lineup to establish excess letdown after determining
need Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 3.1 1-0P-8.5 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U338,340, 345 10 CFR Part 55 Content: 41.5 Comments: KA Match: Item evaluates knowledge of 2 precautions
and further evaluates reason for the 2 precautions
associated
with establishing
Excess Letdown, therefore meeting the KA topic requirement.
MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 6/2008 1.00 Version:0123456789
Answer: B DB DBAACBD Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:33 PM 40
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 21.022 Kl.04 OOIINEW//IllGHERlIROINORTH
ANNAl61200S/
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.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.A Incorrect.
Fans remain running since they are powered from emergency busses not SS busses, chilled water flow is lost but both units are affected, plausible since the electrical
problem relates only to Unit 2.B Correct.As noted above, the mechanical
chiller is powered from Unit 2 SS bus and supplies both units with chilled water.C Incorrect.
Plausible since candidate may assume the electrical
fault would cause a loss of power to the affected equipment and again may only consider Unit 2 affected by the loss of power.o Incorrect.
Plausible since candidate may assume the electrical
fault would cause a loss of power to the affected equipment and again 2nd part of distractor
is correct.Monday, June 30, 2008 3:34:33 PM 41
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY CNTMT Cooling: Knowledge of the physical connections
and/or cause-effect
relationships
between the CCS and the following:
Chilled water Tier: Group: 2 1 Importance
Rating: 2.9 Technical Reference:
1-AP-35, O-AP-10 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 11999 Question History:10 CFR Part 55 Content: CFR: 41.5/43.5/45.3/45.13
Items Not Scrambled NORTH ANNA o123456789 BBBBBBBBBB
Source If Bank: Difficulty
Level: Plant: Previous NRC?: NEW mGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: The item evaluates the status of Chilled Water for Containment
Cooling during a loss of off-site power.MCS Time: 1 Points: 1.00 Version: Answer: Monday, June 30,20083:34:33
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 22.025 AAl.12 098lNEW/IHIGHERJIROINORTH
ANNAl612008INO
Given the following:
- Unit 1 has just entered Mode 4 with cool down to Mode 5 in progress.*RHR Pump1A is in service.*The OATC notes the following:
- RHR Pump 1A motor amps indicate10
and stable.*1-RH-FCV-1605
in automatic indicates 100%demand.Which ONE of the following describes the status of the RHR system and the additional
expected indications?
A.RHR pump 1A cavitating,1-RHR-FCV-1605
operating as designed;Core Exit TCs increasing.
B.RHR pump 1A operating normally, 1-RHR-FCV-1605
failed closed;Core Exit TCs decreasing.RHR pump 1A sheared shaft, 1-RHR-FCV-1605
operating as designed;Core Exit TCs increasing.
D.RHR pump 1A operating normally, 1-RHR-FCV-1605
failed open;Core Exit TCs decreasing.
A Incorrect.
As given amps are low but stable, fluctuating
amps are indication
of cavitation.
For low flow 1-RH-FCV-1605
would be expected to open to try and maintain flow.Inadequate
flow would cause temperature
to increase.8 Incorrect.
The value of 10 and stable is indicative
of a sheared shaft NOT a pump that is operating normally.For the sheared shaft 1-RH-FCV-1605
would be expected to open to try and maintain flow.Inadequate
flow would cause temperature
to increase.C Correct.Normal amps would be around 35, the value of 10 and stable is indicative
of a sheared shaft.For the sheared shaft 1-RH-FCV-1605
would be expected to open to try and maintain flow.Inadequate
flow would cause temperature
to increase.o Incorrect.
The value of 10 and stable is indicative
of a sheared shaft NOT a pump that is operating normally.For the sheared shaft 1-RH-FCV-1605
would be expected to open to try and maintain flow.Inadequate
flow would cause temperature
to increase not decrease, however if flow were high temperature
would decrease.Monday, June 30, 2008 3:34:33 PM 43
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Loss of RHR: Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: RCS temperature
indicators
Question Number: Tier: Group: Importance
Rating: Technical Reference:
3 4 3.8 AP-11, Pages 2-13 actions Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: U430 Bank item with distractor
modifications
41.10 Comments: KA match: The KA is matched because the operational
implication
of loss of RHR during RCS drain-down
is that specific actions must be taken to mitigate the condition.
This item evaluates knowledge of the correct actions during this condition, choosing from actions that may be performed for all conditions
of loss of RHR MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 612008 1.00 Version:0123456789
Answer: C ACD A C CDC D Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO Monday, June 30, 2008 3:34:33 PM 44
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 23.026 A4.01 056INEW//LOWERlIROINORTH
ANNA/6/2008/
Given the following:*A reactor trip and safety injection has occurred.*RCS pressure is 1000 psig and stable.*Containment
pressure is 23 psia and rising slowly.*The crew is performing
1-E-0, Reactor Trip or Safety Injection.
Which ONE of the following describes the appropriate
operator action and the SEQUENCE of the action required?A.CDA is required;ensure CDA is actuated, stop RCPs, verify Quench Spray running, and verify Containment
Isolation Phase B.B.CDA is required;ensure CDA is actuated, stop CC pumps, verify Quench Spray running, verify Containment
Isolation Phase B, and stop RCPs.Quench Spray is required;open Quench Spray Discharge Valves and then start Quench Spray Pumps.D.Quench Spray is required;start Quench Spray Pumps and then open Quench Spray discharge valves.A Incorrect.
CDA would be required if containment
pressure was>28 psia.Plausible because if it was required, these are the correct actions.B Incorrect because CDA is not required.Plausible because it contains all correct actions, but not in the order required.C Correct.Even though CDA is not required, facility has a step in E-O to initiate QSS if containment
is above 20 psia.D Incorrect.
Plausible because many pumps are started with discharge valves closed.In this case, valves are opened first.Monday, June 30, 2008 3:34:33 PM 45
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to manually operate and/or monitor in the control room: CSS controls Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 4.5 1-E-O steps 11/12 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: 41.10 Comments: KA Match: Item evaluates the ability to determine if Quench Spray is required, and since it is required, the actions required (operating
the controls)to initiate it MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW LOWER RO 612008 1.00 Version:0I23456789
Answer:CC BADCB CAD Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:33 PM 46
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 24.026 AA2.0 1 005IBANKINORTH
ANNAlLOWERlIROINORTH
ANNA/6/2008/
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.1A CC Heat Exchanger;
PG water B:'1A CC Heat Exchanger;
Condensate
System C.Non-Regenerative
Heat Exchanger;
PG water D.Non-Regenerative
Heat Exchanger;
Condensate
System A Incorrect.
First part is correct, Service Water pressure is less than CC pressure so this would cause the loss of CC.PG water would not normally be used.B Correct.Service Water pressure is less than CC pressure so this would cause the loss of CC , condensate
is used to fill CCifit is available.
C Incorrect.
Surge tank level would rise since pressure atthatpoint in the letdown system (upstream of PCV-1145)is greater than CC system pressure, source of water plausible but also not correct per the procedure.
o Incorrect.
Surge tank level would rise since pressure at that point in the letdown system (upstream of PCV-1145)is greater than CC system pressure, water source is correct.Monday, June 30, 2008 3:34:33 PM 47
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS Question Number: Tier: Group: 1 1 Importance
Rating: 2.9 Technical Reference:
CC LP, 1-AP-16 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 3663 Question History: 10 CFR Part 55 Content: 41.5,7 Comments: KA Match: Item evaluates knowledge of components
served by CC, and further evaluates knowledge of the makeup sources.The applicant must determine location of a leak in CC to answer this item.NORTH ANNA BANK LOWER RO 612008 Source: Cognitive Level: Job Position: Date: Considered
BANK;although not identical to bank question this item has not been significantly
modified, thus it is classified
as a bank question.MCS Time: 1 Points: 1.00 Version:0123456789
Answer:BCAAAACBDB
Scramble Range:A-D Source If Bank: NORTH ANNA Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:33 PM 48
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 25.026 K2.01 055lNEW/IHIGHERJIROINORTH
ANNN6/2008INO
Given the following on Unit1:*Reactor Trip due to a LOCA.*Safety Injection was actuated 11 minutes ago.*CDA was actuated 7 minutes ago.*RCS pressure is 1125 psig.*Containment
pressure is 29 psia.*RWST level is 72%and lowering.Which ONE of the following describes the operational
status of Inside Recirculation
Spray Pump 1-RS-P-1 8?A.Running;power is supplied directly from 480 volt bus 1J1.NOT running;power is available directly from 480 volt bus 1 J1.C.Running, power is supplied directly from 4160 volt bus 1 J.D.NOT running;power is available directly from 4160 volt bus 1 J.A Incorrect.
The pump will not be running because RWST level is not below 60%.Plausible because the start logic is associated
with CDA and also has a time delay;if candidate is unaware of the aditionallogic (RWST level<60%)they may select this distractor.
Power supply is correct.8 Correct.The pump will not be running because RWST level is not below 60%.Power supply is correct.C Incorrect.
The pump will not be running because RWST level is not below 60%.Plausible because the start logic is associated
with CDA and also has a time delay;if candidate is unaware of the aditionallogic (RWST level<60%)they may select this distractor.
Power supply is correct for Outside Recirc Spray Pumps.D Incorrect.
Correct that the pump will not be running because RWST level is not below 60%.Incorrect because power supply is wrong.Plausible because the power supply is correct for Outside Recirc Spray Pumps.Note: Change in RS pump logic is a recent plant mod making it more likely that the candidate will confuse pump operational
status based on past knowledge.
Monday, June 30, 2008 3:34:33 PM 49
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of bus power supplies to the following:
Containment
spray pumps Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.4 Recirc Spray LP, NCRODP-54 1-E-O, Art.2 1-0P-26A Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 6278 10 CFR Part 55 Content: 41.5 Comments: KA Match: The KA requires knowledge of Spray Pump powersupplies.The
item evaluates knowledge of Spray Pump power supply as well as operation under transient conditions
MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 612008 1.00 Version:0I23456789
Answer: B DCADDDACA Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO Monday, June 30, 20083:34:33
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 26.027 G2.2.42 OlIIMODIFIED//LOWERJIROINORTH
ANNAl61200S1
Given the following:
- Unit 1 is operating at 100%power.*An instrument
failure causes PORV 1-RC-PCV-1455C
to lift.*RCS Pressure is recovering
at a much slower rate than expected.*The operator closes the PORV Block Valve, 1-RC-MOV-1536, and pressure is now 2100 psig and increasing
as expected.*All other equipment appears to be operating normally.Which ONE (1)of the following describes the action(s)required within ONE hour in accordance
with Technical Specifications?
A.Maintain closed and remove power from 1-RC-MOV-1536.
B.Restore RCS pressure to within limits of the COLA.Maintain closed and maintain power to 1-RC-MOV-1536.
D.Place and maintain the PORV in MANUAL control.A Incorrect because for this condition, power does not have to be removed from the block valve.Plausible because it is very close to the correct action, and an interpretation
must be made to determine if seat leakge is occurring.
B Incorrect.
This action is taken, therefore plausible.
However, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is allowed for the action to be taken.C Correct.PORV inoperability
due to excessive seat leakage (as indicated by the conditions
provided)requires that the VALVE IS ISOLATED BY ITS ASSOCIATED
BLOCK VALVE.However power is maintained
to the block to allow quick access if the PORV were needed for pressure control.D Incorrect.
Action would be required if the block valve was inoperable, but plausible because it is easily confused with inoperability
of the PORV itself (controller
not functioning
in auto, place in manual).Monday, June 30,20083:34:34
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Equipment Control:: Ability to recognize system parameters
that are entry-level
conditions
for Technical Specifications.
Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 3.9 TS 3.4.1, 3.4.11 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 12363 10 CFR Part 55 Content: 41.7 Comments: KA Match: Item evaluates LCO entry conditions
for a condition where there is a failure of the pressurizer
pressure control system (PORV failure).MCS Time: Source: Cognitive Level: Job Position: Date: Points: MODIFIED LOWER RO 612008 1.00 Version:0I23456789
Answer:CA ADDBDBDC Scramble Range:A-D Source If Banle Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:34 PM 52
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 27.028 K3.01 027INEW//LOWERlIROINORTH
ANNN6/2008INO
Given the following:
- Both Units were initially at 100%.*The Site experiences
a Loss of Offsite Power.*Unit 1 experiences
a Design Basis Accident with a failure of1H EDG.*Unit 2 is stable in Mode 3 with both Emergency Busses energized from their respective
EDGs.Which ONE of the following describes the operation of the 1-HC-HC-1, Hydrogen Recombiner?
A.1-HC-HC-1 should be placed in service if Containment
Hydrogen concentration
is less than 4%;Power MUST be restored to 1H Bus to place 1-HC-HC-1 in operation.1-HC-HC-1 should be placed in service if Containment
Hydrogen concentration
is less than 4%;Power is available to place 1-HC-HC-1 in operation.
C.1-HC-HC-1 should be placed in service if Containment
Hydrogen concentration
exceeds 4%;Power MUST be restored to 1H Bus to place 1-HC-HC-1 in operation.
D.1-HC-HC-1 should be placed in service if Containment
Hydrogen concentration
exceeds 4%;Power is available to place 1-HC-HC-1 in operation.
A Incorrect.
Either of the two recombiners
may be powered from any of the 4 Emergency Busses;plausible because the candidate may believe that since the recombiners
have unit specific mark numbers they also have unit specific power supplies and most ESF equipment is powered from a dedicated train.The recombiner
is placed in service when CNTMT H2 cone.exceeds 0.5%but is less than 4%, so this portion of the distractor
is correct.B Correct.As stated above, either of the two recombiners
may be powered from any of the 4 Emergency Busses.The recombiner
is placed in service when CNTMT H2 cone.exceeds 0.5%but is less than 4%.C Incorrect.
Either of the two recombiners
may be powered from any of the 4 Emergency Busses;plausible because the candidate may believe that since the recombiners
have unit specific mark numbers they also have unit specific power supplies and most ESF equipment is powered from a dedicated train.At greater than 4%the procedure directs consulting
with TSC, NOT placing recombiner
inservice.
D Incorrect.
First part of distractor
is correct as noted above.At greater than 4%the procedure directs consulting
with TSC, NOT placing recombiner
inservice so this portion is incorrect.
Monday, June 30, 2008 3:34:34 PM 53
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 028 K3.01 Knowledge of the effect that a loss or malfunction
of the HRPS will have on the following:
Hydrogen concentration
in containment
Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 2 3.3 1-E-1 1-0P-63.1 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
10 CFR Part 55 Content: Comments: CFR: 41.7/45.6 MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW LOWER RO 6/2008 1.00 Version: aI23456789 Answer:BBBBBBBBBB Items Not Scrambled Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO Monday, June 30, 2008 3:34:34 PM 54
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 28.029 EKl.05 Ol2IBANKIROBINSON
2001ILOWERlIROINORTH
ANNA/6/2008/
During an ATWS at 100%Reactor Power, EOl conditions, which ONE of the following actions will insert the MOST negative reactivity
within the FI RST 30 seconds of the event?A.Manual Control Rod Insertion B:'Manual Turbine Trip C.Initiation
of Emergency Boration D.Automatic Control Rod Insertion A Incorrect.
Manual control rod insertion will be at 48 steps per minute.Plausible because it is in the first step of FR-S.1 and it does insert negative reactivity.
B Correct.When the turbine is tripped, RCS temperature
and fuel temperature
will rise rapidly, and cause reactor power to be sharply reduced.C Incorrect.
Initiation
of Emergency Boration will also cause negative reactivity
insertion, but will not reach the RCS until several minutes have elapsed in the event.D Incorrect.
Auto rod insertion maximum speed is 72 steps per minute.Plausible because it inserts reactivity
and is the first control system response to the A TWS, but does not insert as much negative reactivity
as a turbine trip.Monday, June 30, 2008 3:34:34 PM 55
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the operational
implications
of the following concepts as they apply to the ATWS: definition
of negative temperature
coefficient
as applied to large PWR coolant systems Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 2.8 FR-S.1 SD Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 11570 10 CFR Part 55 Content: 41.5 Comments: KA Match: Item evaluates the action or plant response that would add the most negative reactivity, which is a direct relation to negative temperature
coefficient.
Therefore, it evaluates applicants
knowledge of the definition
of negative temperature
coefficient
MCS Time: Source: Cognitive Level: Job Position: Date: Points: BANK LOWER RO 612008 l.00 Version:0I2345 6:]89 Answer:BBDAACCBDB
Scramble Range:A-D Source If Bank: ROBINSON 200 I Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:34 PM 56
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 29.029 K4.03 077INEW/ILOWERJIRO/NORTH
ANNAl6/20081
Given the following:
- Both units are in Mode 5.*Containment
Purge is in progress on each unit in preparation
for Containment
entry.*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 describes the effect of these conditions
on the Containment
Purge once all automatic actuations
have taken place?A.Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B trip;Containment
Purge Supply isolation valves close on BOTH units.B.ONLY Purge Supply Fan 1-HV-F-4A trips;ONLY Unit 1 Containment
Purge Supply isolation valves close.C.Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B remain running;ONLY Unit 1 Containment
Purge Supply isolation valves close.Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B trip and then automatically
start;ONLY Unit 1 Containment
Purge Supply isolation valves close.A Incorrect.
Plausible because the Purge Supply fans do trip, but valves on unaffected
unit do not close.B Incorrect.
Plausible because the 4A fan control switch is on Unit 1 and the 4B on Unit 2, and it is logical to believe that Unit 2 will be unaffected.
C Incorrect.
Plausible because with 2 units being purged, the affected unit will isolate, and there is still a flowpath for fans to operate as required without interuption.
o Correct.The purge fans will initially trip however once the valves on the affected unit close the logic is satisfied for the fans to restart (valves on unaffected
unit remain open and the release flow path from the affected unit is isolated).
Monday, June 30, 2008 3:34:34 PM 57
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of design feature(s)
and/or interlock(s)
which provide for the following:
Automatic purge isolation Question Number: Tier: Group: 2 2 Importance
Rating: 3.2 Technical Reference:
Primary Ventilation
LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 4494, 4492 Question History: 10 CFR Part 55 Content: 41.11 Scramble Range:A-D NORTH ANNA NEW LOWER RO 612008 Comments: KA Match: Item evaluates an abnormal condition requiring an automatic containment
purge isolation, and therefore directly meets the required topic MCS Time: 1 Points: 1.00 Version:0123456789
Answer: DB BACACBDA Source If Bank: Difficulty
Level: Plant: Previous NRC?: 'Source: Cognitive Level: Job Position: Date: Monday, June 30, 2008 3:34:34 PM 58
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 30.032 AK3.01 026IBANKlHARRISIHIGHERJIROINORTH
ANNA/6/2008/
Given the following conditions:*A reactor startup is inprogressand
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
6X1 0 3 CPS and trending up slowly.Which one of the following describes the required operator response and the reason for the response?A':'Suspend the reactor startup;with only one source range channel operable, there is inadequate
protection
against an uncontrolled
rod withdrawal.
B.Suspend the reactor startup;source range channels are currently not required to trip the reactor, however, the source range monitoring
functions must be available.
C.Continue the reactor startup;the Intermediate
Range Neutron Flux Trip and the Power Range Neutron Flux-Low Trip provide the necessary core protection.
D.Continue the reactor startup;with only one source range channel operable 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is allowed to restore two channels to service.A Correct.With only 1 Source Range available below P-6, (10-10 amps), the startup must be stopped because a single failure would now make the SR high flux trip unavailable.
B Incorrect.
Plausible because tech specs requires the SR in lower modes, and this would be true if rod control was not capable of withdrawal.
C Incorrect.
Plausible because the SR provides redundant protection
to these trips.D Incorrect.
Plausible because this is the normal TS action statement if rods were not capable of withdrawal.
Monday, June 30, 2008 3:34:34 PM 59
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the reasons for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation:
Startup termination
on source-range
loss Question Number: Tier: Group: 1 2 Importance
Rating: 3.2 Technical Reference:
TS 3.3.1 and basis Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 10390 Question History: 10 CFR Part 55 Content: 41.7,43.2 Comments: KA Match: Item evaluates knowledge of the reason for startup termination
as well as whether termination
is required, based on plant conditions
that require operability
of the instrument
NORTH ANNA 0123456789
ACCCB DADB A Scramble Range:A-D Source If Bank: HARRIS Difficulty
Level: Plant: Previous NRC?: Version: Answer: 1.00 Points: BANK HIGHER RO 612008 Source: Cognitive Level: Job Position: Date: Item was previously
developed for Harris, but has been editorially
modified with a different reason on correct answer and shuffled distractors, as well as modified wording on plant conditions.
MCS Time: Monday, June 30, 2008 3:34:34 PM 60
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 31.033 K4.05 028IBANKINORTH
ANNAILOWERJIRO/NORTH
ANNN6/2008NES
Which ONE of the following describes the preferred method for maintaining
Spent Fuel Pool water volume and Subcriticality
Margin?Minimum required boron concentration
is...A.2500 ppm.Leakage is compensated
for by making up from the blender with PG water.B.2500 ppm.Leakage is compensated
for by making up from the blender with blended flow.2600 ppm.Evaporation
is compensated
for by making up from the blender with PG water.D.2600 ppm.Evaporation
is compensated
for by making up from the blender with blended flow.A Incorrect.
2500 ppm is incorrect but plausible because it is the minimum boron concentration
allowed for SI Accumulators.
B Incorrect.
2500 ppm is incorrect but plausible because it is the minimum boron concentration
allowed for SI Accumulators.
Boric Acid blender is used for makeup when leakage is evident.C Correct.Minimum boron concentration
per TS-3.9.1 is 2600 ppm.PG water is used to makeup for evaporation.
Boric Acid blender is used for makeup when leakage is evident.o Incorrect.
Minimum boron concentration
per TS-3.9.1 is 2600 ppm, however normal makeup for evaporation
is with PG water since boron does not carry over with evaporation.
Monday, June 30, 2008 3:34:34 PM 61
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 041508 RO ONLY Knowledge of design feature(s)
and/or interlock(s)
which provide for the following:
Adequate 80M (boron concentration)
Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 2 3.1 T8 3.9.1, NCROOP-49-NA
1-0p-16.5 Proposedreferencesto
be provided to applicants
during examination:
None Learning Objective:
U 4472, U-3749 10 CFR Part 55 Content: 41 Comments: KA Match: Item matches KA because it evaluates knowledge of T8 requirement
for minimum boron concentration, which provides for adequate 80M.PG water could potentially
reduce 80M, so boron concentration
for 8FP has a T8 minimum.Changed PPM for distractors
for added plausibility;
shuffled options MCS Time: Source: Cognitive Level: Job Position: Date: Points: BANK LOWER RO 6/2008 1.00 Version:0123456789
Answer: CDCBBCB DC C Scramble Range:A-D Source If Bank:: NORTH ANNA Difficulty
Level: Plant: NORTH ANNA Previous NRC?: YES Monday, June 30, 2008 3:34:34 PM 62
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 1508 RO ONLY 32.036 AAI.Ol 027INEW/IHIGHERlIROINORTH
ANNN6/2008/
Given the following:
- Unit 1 is in Mode6with 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 describes the expected indications
and response of the Primary Ventilation
System?A.Vent Stack'B'Radiation Monitor indication
increases;
Containment
Purge Exhaust automatically
isolates when Vent Stack'B'Radiation Monitor exceeds alarm setpoint.Vent Stack'B'Radiation Monitor indication
increases;
Containment
Purge Exhaust should be manually diverted through the Auxiliary Building Iodine Filters.C.Vent Stack'A'Radiation Monitor indication
increases;
Containment
Purge Exhaust automatically
isolates when Vent Stack'A'Radiation Monitor exceeds alarm setpoint.D.Vent Stack'A'Radiation Monitor indication
increases;
Containment
Purge Exhaust should be manually diverted through the Auxiliary Building.Iodine Filters A Incorrect.
First portion is correct Purge exhaust is directed through Vent Stack B.Second portion of distractor
is incorrect but plausible since several different functions will isolate Containment
Purge automatically.
B Correct.First portion is correct as noted above.Second portion is correct as procedure AP-5 provides guidance to direct Purge Exhaust through the Iodine Filter Bank to reduce release activity.C Incorrect.
First portion is incorrect Purge exhaust is directed through Vent Stack B, but the candidate who is unfamiliar
with Primary Ventilation
System may select this distractor.
Second portion of distractor
is incorrect but plausible since several different functions will isolate Containment
Purge automatically.
D Incorrect.
First portion is incorrect as noted above.Second portion is correct as procedure AP-5 provides guidance to direct Purge Exhaust through the Iodine Filter Bank to reduce release activity.Monday, June 30, 2008 3:34:34 PM 63
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to operate and/or monitor the following as they apply to the Fuel Handling Incidents:
Reactor building containment
purge ventilation
system Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 2 3.3 O-AP-30 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
None Question History: 10 CFR Part 55 Content: 41.10 Comments: KA match because the item evaluates knowledge of the operation of the Containment
Purge system, specific to a Fuel Handling Accident.The item further evaluates containment
isolation by testing knowledge of allowable containment
closure time.MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 612008 1.00 Version: aI23456789 Answer: B DC DCABAAD Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:35 PM 64
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 33.039 G2.1.32 057INEW//LOWERlIROINORTH
ANNA/6/20081
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 the mal overload of breaker for NRV due to excessive DP when opening the NRV.Prevent excessive swell of SG volume.C.Prevent inadvertent
Hi Steam Line Differential
Pressure SI.D.Prevent damage to valve internals due to excessive DP when opening the NRV.A Incorrect.
Plausible since there have been industry events related to rotor lockup, however at this point in the procedure the concern is for swell and loss of level control.B Correct.A rapid presssure drop would occur if the valve were opened against a substantial
DIP,thisinturn
would result in excessive swell and the potential to loose control of Sg level.C Incorrect.
A high steam line differential
pressure would not actually be received when opening an NRV.Plausible because an isolated main steam line will have a different pressure than in-service
main steam lines.D Incorrect.
NRVs are designed to operate against high DPs, but plausible because mechanical
binding of valves due to excessive DP is a known occurrence.
Monday, June 30, 2008 3:34:35 PM 65
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Conduct of Operations:
Ability to explain and apply all system limits and precautions.
Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.8 1-0P-28.1 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: U 10085 41.10 Comments: KA Match: Item evaluates knowledge of a main steam system precaution
and correct answer provides the explanation
of why the caution is observed.MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW LOWER RO 6/2008 1.00 Version:0123456789
Answer: B BADDCDDDD Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:35 PM 66
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 34.041 K6.03 002INEW//HIGHER//RO/NORTH
ANNA/6/2008/
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-Tref deviation indicates 11 degrees F.*1 M-D4, STEAM DUMP ARMED, is illuminated.
Which ON E of the following describes Steam Dump response?A.Two banks of Steam Dumps are modulating
open.Two banks of steam dumps are closed.Two banks of Steam Dumps are tripped open.One bank of steam dumps is modulating
open.C.Two banks of Steam Dumps are tripped open.Two banks of steam dumps are modulating
open.D.Four banks of steam dumps are tripped open.A Incorrect.
At 10 degrees, 2 steam dump banks trip open in load reject mode.This value is different for turbine trip mode.The 3rd bank of dump valves will be modulating, and the 4th bank has not yet reached setpoint.Plausible because they are modulating
up to 10 degrees.B Correct.As discussed above both the trip open and modulate functions of the load rejection program are satisfied.
C Incorrect.
Plausible because two banks are tripped open.One other bank is modulating, but the 4th has not yet started to open.It would be opening in another 2 degrees, and if candidate is unaware of overlap within the banks they may choose this distractor.
D Incorrect.
Plausible, because the next trip open setpoint will be all 4 banks;5 degrees additional
will cause them to trip open.Monday, June 30, 2008 3:34:35 PM 67
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the effect of a loss or malfunction
on the following will have on the SDS: Controller
and positioners, including ICS, S/G, CRDS Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 2 2.7 Steam Dump LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 8865, U 8866 10 CFR Part 55 Content: 41.5 Comments: KA Match: Item evaluates failure of a turbine control valve (SG)on the operation of the steam dump system.(Westinghouse
has no ICS and CRDS has no different consequence (no control input>>MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 6/2008 1.00 Version: aI23456789 Answer: B DADDC BAD A Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:35 PM 68
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 35.054 AK3.01 015INEW/IHIGHERI/RO/NORTH
ANNN6120081
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-F1/F2/F3, SG 1 A/1 B/1 C LEVEL ERROR*1F-D1/D2/D3, STM GEN 1A/1B/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'I Trip the reactor;prevents a challenge to the Reactor Protection
System from loss of secondary heat sink.B.Trip the reactor;prevents damage to operating Main Feedwater Pump due to pump runout flow and cavitation.
C.Reduce load;reduces steam flow to within the capacity of the operating MFW pump.D.Reduce load;prevent operating MFW pump windings from overheating
due to excessive current.A Correct.1B MFW pump cannot be started and with power at 75%and only 1 MFW pump available a reactor trip is initiated since one would otherwise occur automatically.
Basis for this reactor trip is the loss of secondary heat sink.B Incorrect.
Correct response for condition but although pump may experience
runout the basis is ensuring core protection, not equipment longevity which may be adversely affected by a brief period of operation at high flow conditions.
C Incorrect.
Power is at 75%and therefore only slightly above the value for which this would be the correct response.The 2nd half of the distractor
is true, power reduction will reduce steam flow and thus ease the burden on the remaining MFW pump.D Incorrect.
As noted above and plausiblesincesince
increased flow demand will causes significantly
higher current if power remained at the edge of capacity of the pump.Monday, June 30,20083:34:35
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Reactor and/or turbine trip, manual and automatic Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 4.1 1-AP-31, TS Basis 3.3.1 (SG LO-LO)Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: Comments: MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 6/2008 1.00 Version:0123456789
Answer: ACCAA DBCBB Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:35 PM 70
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 36.055 A3.03 081INEW//LOWERlIROINORTH
ANNA/6/20081
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-0, 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 HI-HI radiation;
steam supply to air ejectors isolated on HI-HI radiation.
B.Exhaust diverted to Containment
on HI-HI radiation;
steam supply to air ejectors isolated on HI-HI radiation.
C.Exhaust diverted to Containment
on Phase A isolation;
steam supply to air ejectors isolated on Phase A isolation.Exhaust isolated on Phase A isolation;
steam supply to air ejectors isolated on Phase A isolation.
A Incorrect.
Plausible because isolation of both supply and discharge is logical on a hi-hi radition signal to prevent release.B Incorrect.
First half is correct and second half is plausible for same reason as A.C Incorrect.
Second half is correct and first half is plausible because it would prevent radioactive
release to the environment.
D Correct.Discharge aligns to Containment
via 2 trip valves.Normal discharge valve closes on hi-hi radiation.
In the event of Phase A, discharge and steam supply isolate.Monday, June 30, 2008 3:34:35 PM 71
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to monitor automatic operation of the CARS, including:
Automatic diversion of CARS exhaust Question Number: Tier: Group: 2 2 Importance
Rating: 2.5 Technical Reference:
Condensate
LP, 1-AP-24 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U4007 Question History: 10 CFR Part 55 Content: 41.5 Scramble Range: A-D NORTH ANNA oI23456789 DACBABCCDB
Source If Bank: Difficulty
Level: Plant: Previous NRC?: NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates parameter that causes automatic divert of air ejector exhaust as well as what causes complete isolation MCS Time: I Points: 1.00 Version: Answer: Monday, June 30, 2008 3:34:35 PM 72
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 37.055 EAI.06 016INEW/IHIGHERlIROINORTH
ANNA/6/2008/
Given the following:*A loss of all AC Power has occurred.*The crew is performing
actions of 1-ECA-0.O, Loss of All AC Power.*1H EDG has failed and CANNOTberestarted.
- The crew is performing
1-ECA-0.0, Attachment
4, Attempting
to restore power to1H (1J)Emergency Bus.*Attempts to start EDG1J are in progress.*RCP Seal Water Outlet temperature
is 2000F and rising at 2°F per minute.Which ONE of the following describes the action required in accordance
with ECA-O.O?A.Place Charging Pumps in PTL prior to attempting
to start1J EDG in MANUALLOCAL.B.Perform Attachment
3, RCP seal isolation, prior to attempting
to start1J EDG in MANUAL-LOCAL.Place 1J EDG in MANUAL-LOCAL, press EMER GEN Alarm&Shutdown RESET Button, and verify Shutdown Relay Status Light is lit.After one minute, place1J EDG in MANUAL-REMOTE and determine if the EDG starts.D.Place 1J EDG in MANUAL-REMOTE, press EMER GEN Alarm&Shutdown RESET Button, and verify Shutdown Relay Status Light is lit.After one minute, place1J EDG in MANUAL-LOCAL and determine if the EDG starts.A Incorrect.
This would be performed if RCP seal return temperature
was 235 degrees F or greater.Plausible because it is an action that must be considered.
B Incorrect.
As noted above this would be correct if RCPs crossed the 235 degree threshold.
C Correct.Actions are correct for starting the EDG.They are not all inclusive but do not need to be;based on the information
in the stem it is reasonable
to conclude that RCP sealleakoff
has not heated up excessively.
D Incorrect.
The EDG must be reset in MANUAL LOCAL, and will not reset if these actions are reversed.Plausible because it requires detailed knowledge of the emergency shutdown circuitry of the EDG.Monday, June 30, 2008 3:34:35 PM 73
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to operate and monitor the following as they apply to a Station Blackout: Restoration
of power with one ED/G Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 4.1 ECA-O.O Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: U 5687 41.10,41.7
Comments: KA Match: Item evaluates operation of the EDG that is being used to restore power.Part of the procedure for restoration
requires knowledge of RCP seal status as well as switch manipulation
for restoration
MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 6/2008 1.00 Version:0123456789
Answer:CACBA CDC DC Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30,20083:34:35
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 38.056 AA2.72 018lNEW/IHIGHERlIROINORTH
ANNA/6/20081
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.AFW flow available through the HCV header;flow initiates as soon as the 4160 Volt emergency bus is energized.AFW flow available through the MOV header;flow initiates as soon as the 4160 Volt emergency bus is energized.
C.AFW flow available through the HCV header;flow initiates approximately
20 seconds after the 4160 Volt emergency bus is energized.
D.AFW flow available through the MOV header;flow initiates approximately
20 seconds after the 4160 Volt emergency bus is energized.
A Incorrect.
Bus1H supplies power to the MDAFW Pump 3A which is normally aligned to the HCV header.Plausible because each MDAFW pump is aligned to 1 header, and the applicant may not know which is which.B Correct.450 GPM AFW flow is available on the MOV header from MDAFW 3B and will be supplied without delay since this is a LOOP vice LOOP/LOCA scenario.C Incorrect.
Plausible as in A, and also plausible because AFW is on a 20 second time delay for SI initiation.
Applicant may confuse sequencer operation for LOOP.D Incorrect.
Plausible as described in C, but correct header provided in this distractor.
Monday, June 30, 2008 3:34:35 PM 75
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Auxiliary feed flow Question Number: Tier: Group: 1 1 Importance
Rating: 4.1 Technical Reference:
NCRODP-26, AFW LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 6035 U 6037 Question History: 10 CFR Part 55 Content: 41.5 Scramble Range:A-D NORTH ANNA o123456789 BABCABBBAA
Source If Banle Difficulty
Level: Plant: Previous NRC?: NEW HIGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates AFW flow alignment in an event specific to loss of off-site power as opposed to a safety injection signal.Additionally, the applicant must determine which header the flow will be from.MCS Time: 1 Points: 1.00 Version: Answer: Monday, June 30, 2008 3:34:35 PM 76
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 39.057 G2.4.45 039lNEW/IHIGHERlIROINORTH
ANNAl612008INO
The Unit is in MODE 3 preparing to startup.10 minutes ago a loss of vital bus 1-1 occurred and power has not yet been restored.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 NOT yet required.B.Monitor RCP temperatures
due to loss of CC flow;Notification
of State and Local authorities
is required within the next 15 minutes.C.Monitor SG PORVs due to loss of condenser steam dumps;Notification
of State and Local authorities
is NOT yet required.D.Monitor SG PORVs due to loss of condenser steam dumps;Notification
of State and Local authorities
is required within the next 15 minutes.A Correct.AP-10 att.24 directs the need to monitor RCPs which will overheat in-10 minutes with no CC flow.Loss of all control room annunciators
is E-plan entry but not until 15 minutes has elapsed.B Incorrrect.
First part is ok but threshold for notification
not crossed.C Incorrect.
This action is correct for loss of bus 1-111, not 1-1.Loss of all control room annunciators
is E-plan entry but not until 15 minutes has elapsed.D Incorrect.
This action is correct for loss of bus 1-11I, not 1-1.As noted above no E-plan threshold has been crossed.Monday, June 30,20083:34:35
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Loss of Vital AC Bus: Emergency Procedures
/Plan: Ability to prioritize
and interpret the significance
of each annunciator
or alarm.Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 4.1 0-AP-10, EPIP 1.01 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: CFR: 41.10/43.5/45.3/45.12 Comments: MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 612008 l.00 Version: Answer: o 123456789 AAAAAAAAAA
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Items Not Scrambled NORTH ANNA NO Monday, June 30, 20083:34:36
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 40.058 AKI.OI 039IMODIFIED//IllGHER//ROINORTH
ANNA/6/2008/
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:*1 H-B3, BATIERY CHGR 1-111 TROUBLE*Battery Charger 1-111 DC Output breaker has tripped and CANNOT be reset.*DC Bus 1-111 voltage is 118 volts and lowering.Which ONE of the following describes the action that will be taken to restore DC Bus 1-1I1?A.Place Swing Battery Charger 1 C-I in service with the NORMAUEQUALIZE
switch in NORMAL.B.Place Swing Battery Charger 1 C-I in service with the NORMAUEQUALIZE
switch in EQUALIZE.Place Swing Battery Charger 1 C-II in service with the NORMAUEQUALIZE
switch in NORMAL.D.Place Swing Battery Charger 1 C-II in service with the NORMAUEQUALIZE
switch in EQUALIZE.A.Incorrect.
Swing Charger 1-1 would be placed in service for a loss of Charger 1-1 or 1-11.DC Bus 1-111 and 1-IV are supplied by Swing Charger 1-11.Switch position is correct.B Incorrect.
Switch position would be equalize only if the battery charger that tripped was in equalize mode.By all DC Bus voltage being 131 VDC prior to the charger trip, applicant should be able to determine that the chargers were all in NORMAL.C Correct.DC Bus 1-111 and 1-IV are supplied by Swing Charger 1-11.Switch position is correct.D Incorrect.
Wrong switch position is indicated.
As noted in B voltage being 131 VDC prior to the charger trip, applicant should be able to determine that the chargers were all in NORMAL.Monday, June 30, 2008 3:34:36 PM 79
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the operational
implications
of the following concepts as they apply to Loss of DC Power: Battery charger equipment and instrumentation
Question Number: Tier: 1 Group: 1 Importance
Rating: 2.8 Technical Reference:
1-0P-26.4.3,0-AP-10
Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 5509 10 CFR Part 55 Content: 41.10 Comments: KA Match: Item evluates knowledge of Charger equipment by evaluating
position of the NORMAUEQUALIZE
switch based upon conditions
given in the stem.Item was modified from 2006 test item.Different bus failure and different 2nd half of options MCS Time: Source: Cognitive Level: Job Position: Date: Points: MODIFIED IDGHER RO 6/2008 1.00 Version:0123456789
Answer:CBDC CD A D CD Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30,20083:34:36
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 41.059 KI.02 059IMODIFIEDIIHIGHERlIROINORTH
ANNN6120081
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 been exceeded;AFW Pumps are running.B.A reactor trip setpoint has been exceeded;AFW Pumps are NOT running.A reactor trip setpoint has NOT been exceeded;AFW Pumps are running.D.A reactor trip setpoint has NOT been exceeded;AFW Pumps are NOT running.A Incorrect.
RPS trip setpoint was not exceeded, because the steam flow/feed flow mismatch is not active until SG level reaches 25%.Plausible because the steam flow/feed flow mismatch causes a trip at higher than normal SG level trip setpoints.
AFW pumps started when all 3 Feed Pumps were tripped.B Incorrect.
See A.AFW pumps are running, but plausible because the applicant may apply the auto start at 18%in any SG level and omit the loss of all feed pumps start.C Correct.Logic for Reactor trip is not met as noted above, but AFW auto start met based on information
provided in stem.D Incorrect.
Logic for Reactor trip is not-met as noted above, AFW pumps are running, but plausible because the applicant may apply the auto start at 18%in any SG level and omit the loss of all feed pumps start.Monday, June 30, 2008 3:34:36 PM 81
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the physical connections
and/or cause-effect
relationships
between the MFW and the following AFW system Question Number: Tier: Group: 2 1 Importance
Rating: 3.4 Technical Reference:
NCRODP-26, AFW LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 6035, 6037 Question History: 10 CFR Part 55 Content: 41.7,41.5 Scramble Range:A-D NORTH ANNA o12 3456789 CCACBAAABB
Source If Bank: Difficulty
Level: Plant: Previous NRC?: MODIFIED HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates cause-effect
releationship
of Main Feed Pump trip vs.AFW pump auto start circuitry.
MCS Time: 1 Points: 1.00 Version: Answer: Monday, June 30, 2008 3:34:36 PM 82
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 42.060 AAl.05 029INEW//LOWERlIRO/NORTH
ANNN6/20081
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&B HI HI RADIATION Which ONE of the following describes the statusofof the Gas Decay Tank release lineup?Flow Control valve 1-GW-FCV-101
closed when 1-GW-RI-178-1
high radiation alarm was received.Pressure Control valve 1-GW-PCV-117
does NOT receive a close signal.B.Flow Control valve 1-GW-FCV-101
AND Pressure Control valve 1-GW-PCV-117
closed when 1-GW-RI-178-1
high radiation alarm was received.C.Flow Control valve 1-GW-FCV-101
remained open UNTIL 1-GW-RI-178-2
high radiation alarm was received.Pressure Control valve 1-GW-PCV-117
does NOT receive a close signal.D.Flow Control valve 1-GW-FCV-101
AND Pressure Control valve 1-GW-PCV-117
remained open until1-GW-RI-178-2
high radiation alarm was received.A Correct.178-1 initiates closure of the flow control valve, but the pressure control valve does not receive a close signal.B Incorrect.
178-1 initiates cloure but the PCV does not receive a close signal.Plausible because the pressure control valve is at the inlet to the FCV and part of the discharge flow path.C Incorrect.
The discharge flowpath will already be closed when the high range monitor goes into alarm.Plausible because it is logical to believe that the high range monitor will initiate control action.D Incorrect.
See C as well as B for plausibility.
Monday, June 30, 2008 3:34:36 PM 83
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 1508 RO ONLY Ability to determine and interpret the following as they apply to the Accidental
Gaseous Radwaste: That the automatic safetyactionshave
occurred as a result of a high ARM system signal Question Number: Tier: Group: 1 2 Importance
Rating: 3.7 Technical Reference:
NCRODP-45, GW LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 10705 Question History: 10 CFR Part 55 Content: 41.11 Scramble Range:A-D (Accidental
NORTH ANNA Comments: KA Match: Item evaluates isolation of gaseous waste release on high radiation.
release occurring if abnormal radiation is present)MCS Time: I Points: 1.00 Version:0I23456789
Answer: ACB CDC CDDD Source If Bank: Difficulty
Level: Plant: Previous NRC?: Source: Cognitive Level:.LOVVER Job Position: RO Date: 612008 Monday, June 30, 20083:34:36
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 43.061 G2.4.3 030INEW//LOWER//RO/NORTH
ANNN61200S/
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.Monitor green light ON;annunciator
received on Unit 1.B,...Monitor green light ON;annunciator
received on Unit 2.C.Monitor green light OFF;annunciator
received on Unit 1.D.Monitor green light OFF;annunciator
received on Unit 2.A Incorrect.
Green monitor light would be on and plausible because it is logical to assume that the high radiation alarm (RAD TROUBLE)is on the associated
unit.B Correct.Green monitor light would be on and high radiation alarm (RAD TROUBLE)is on Unit 2.C Incorrect.
Amber and red lights indicate alarm, but green light off (SAFE/RESET
LIGHT)would indicate a monitor failure.Plausible also because it is logical to assume that the high radiation alarm (RAD TROUBLE)is on the associated
unit.D Incorrect.
Amber and red lights indicate alarm, but green light off (SAFE/RESET
LIGHT)would indicate a monitor failure.Correct Unit for annunciator
provided in this distractor.
Monday, June 30,20083:34:36
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Emergency Procedures
/Plan: Ability to identify post-accident
instrumentation.
Question Number: Tier: Group: 1 2 Importance
Rating: 3.7 Technical Reference:
NCRODP-46, RMS LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 5248, 5250 Question History: 10 CFR Part 55 Content: 41.11 Scramble Range:A-D NORTH ANNA NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: item evaluates recognition
of alarm status of the post accident monitor required by technical specifications, therefore KA is met.(identification
of indication
and alarm)MCS Time: 1 Points: 1.00 Version:0123456789
Answer: BADCCADB CA Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday.June 30,20083:34:36
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 44.061 K2.01 060lNEW/ILOWERJIROINORTH
ANNAl6/2008INO
Which ONE of the following states the power supplies to AFW Discharge MOVs, 1-FW-MOV-100A, B, C?A.MCC 1 H1-2N B:o'" MCC 1J1-2N C.1A Semi-Vital
Bus D.1B Semi-Vital
Bus A Incorrect.
The AFW discharge HCVs are powered from1H bus through semi vital bus 1 A.Plausible because the valves are safety related and all valves are ultimately
powered from either H or J trains.B Correct all valves listed poweredfromthis MCC.C Incorrect.
AFW Discharge HCVs (1-FW-HCV-1
OOA, B, C)are powered from this source.Plausible because the valves and power supplies are easily confused, since there are no train designators.
D Incorrect.
Semi-Vital1A
supplies AFW Discharge HCVs.Semi-Vital1B
does not provide power to AFW discharge valves, but since the opposite bus does, and there are no train designators, this supply is credible.Knowledge of bus power supplies to the following:AFW
system MOVs Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.2 NCRODP-26, Table 26-3;AFW Lesson Plan 1-0P-26A Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 5980 10 CFR Part 55 Content: 41.5 Comments: KA Match: Topic directly matches the KA as it evaluates knowledge of the power supply to AFW discharge MOVs, as required by KA topic.Monday, June 30, 2008 3:34:36 PM 87
Scramble Range:A-D NEW LOWER RO 612008 QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Time: 1 Points: 1.00 Version:0123456789
Answer: BADAAABABA
Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO MCS Source: Cognitive Level: Job Position: Date: Monday, June 30, 2008 3:34:36 PM 88
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 45.062 G2.1.27 061 IBANKINORTH
ANNAILOWER//ROINORTH
ANNN6120081
A disconnect
switch is at the output of vital bus inverters 1-1 and 2-1 in order to A.dedicate the associated
Sola transformer
to supply power to its vital bus onlydedicate the associated
inverter to supply power to the opposite unit's channel 1 ex-core flux monitor C.isolate the associated
inverter from its vital bus for maintenance
D.isolate the associated
Appendix-R
power panel for maintenance
A Incorrect.
Purpose of bypass switch is for SOLA to supply the vital bus.Plausible because the bypass and disconnect
could be confused.B Correct.This is a design feature for Safe Sutdown function that ensures capability
to monitor reactor subcriticallity.
C Incorrect.
The Inverter Output breaker would be used to disconnect
the inverter from the bus.Plausible because the function could potentially
be used, but is not the purpose.o Incorrect.
Appendix R panels are isolated by transfer switches.Plausible because disconnects
do perform an isolation function, and the disconnects
are provided in case of a fire that destroys the vital bus.Conduct of Operations:
Knowledge of system purpose and/or function.Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.9 Vital AC LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 5534 10 CFR Part 55 Content: 41.5 Comments: KA Match: Item evaluates one of the functions of the 120 VAC vital distribution
system, in that cross-tie between units is available Monday, June 30, 2008 3:34:36 PM 89
NORTH ANNA BANK LOWER RO 612008 QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Time: 1 Points: 1.00 Version:0123456789
Answer:BAACCDBDB B Scramble Range:A-D Source If Bank: NORTH ANNA Difficulty
Level: Plant: Previous NRC?: MCS Source: Cognitive Level: Job Position: Date: Monday, June 30, 2008 3:34:36 PM 90
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 46.062 K3.03 062INEW//LOWERlIROINORTH
ANNN6120081
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.1-1 and 1-111-111 and 1-IV C.2-1 and 2-11 D.2-111 and 2-IV A Incorrect.
Chargers 1-1 and 1-11 are supplied from 480 volt bus 1 H, which is supplied from 4.16KV Bus 1 H, which is supplied from Transfer Bus F.Plausible because each of the 4 KV busses have anormalsupply
from transfer bus D, E, or F.Alternate supplies are from SSTs or from Emergency Diesel Generators.
B Correct.Chargers 1-111 and 1-IV are supplied from Bus 1J, which receives power from Transfer Bus D.If Transfer Bus D is deenergized, alternate power will be supplied from Unit 2 SST 2B or from1J EDG.Power will be temporarily
interrupted
to the bus.C Incorrect.
Loss of transfer Bus E would cause loss of the 2-1 and 2-11 chargers.Plausible same reason as A, all are supplied from the Transfer Busses.D Incorrect.
Plausible as in A, Transfer Bus F is the normal supply to 2J, which supplies chargers 2-111 and 2-IV.Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the effect that a loss or malfunction
of the ac distribution
system will have on the following:
DC system Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 3.7 NCRODP Figure 35-1 NA 1-0P-26A O-AP-10 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 5511 10 CFR Part 55 Content: 41.7 Comments: KA Match: Item directly evaluates a loss of AC power to the DC distribution
system by evaluating
knowledge of which Transfer Bus supplies the emergency bus that provides power to specific vital battery chargers, thus demonstrating
knowledge of the effect of a loss of AC on the DC distribution
system.MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW LOWER RO 612008 1.00 Version:0I23456789
Answer:BAA BADACBD Scramble Range:A-D Source If Bank:: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 47.063 K4.01 063IBANKINORTH
ANNAlHIGHERlJROINORTH
ANNA/6/2008/
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.Static switch transfer occurs;vital DC bus voltage initially decreases by several volts and then continues to decrease at a faster rate over time.B.Static switch transfer occurs;vital DC bus voltage initially decreases by several volts and then continues to decrease at the same rate over time.NO static switch transfer;vital DC bus voltage initially decreases by several volts and then continues to decrease at a faster rate over time.D.NO static switch transfer;vital DC bus voltage initially decreases by several volts and then continues to decrease at the same rate over time.A Incorrect.
If the charger is lost, battery will supply the inverter due to the changed bias on the blocking diode.Plausible because loss of inverter input(both)results
in static switch transfer.Second part is true rate of voltage decay increases over time due to cell reversal.B Incorrect.
As noted above conditions
DO NOT exist to warrant a transfer.Second part is incorrect but plausible since the candidate may not be aware of the effect of cell reversal on the battery.C Correct.Inverter will remain powered by it's associated
DC bus so no transfer will occur.Second part is also true as the rate of voltage decay increases over time due to cell reversal.D Incorrect.
Inverter will remain powered by it's associated
DC bus so no transfer will occur.Second part is incorrect but plausible since the candidate may not be aware of the effect of cell reversal on the battery.Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of dc electrical
system design feature(s)
and/or interlock(s)
which provide for the following:
Manual/automatic
transfers of control Question Number: Tier: Group: 2 1 Importance
Rating: 2.7 Technical Reference:
Vital Electrical
LP/SD Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 9619 Question History: 10 CFR Part 55 Content: 41.7 NORTH ANNA BANK HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates knowledge of a failure of the DC Electrical
Distribution
system and its effect on the transfer of vital AC inverters.
The question in effect is asking knowledge of an automatic transfer of control to the battery when a charger fails, against the automatic transfer of control to a regulating
transformer
via static switch MCS Time: 1 Points: 1.00 Version:0123456789
Answer: CDBB ABC DCA Scramble Range:A-D Source If Bank: NORTH ANNA Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:37 PM 94
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 48.064 K3.02 064INEW//HIGHER//ROINORTH
ANNAl612008/
Given the following:*A lightning strike has occurred resulting in a loss of the North Anna Switchyard.
- The 1 J 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-0, Reactor Trip or Safety Injection, and manually actuated SI.Which ONE of the following describes the reason that no J Train ESF equipment is running?A.1 J EDG did NOT start due to loss of the auxiliary fuel oil pump.B:'1 J EDG did NOT start due to loss of power to both start circuits.C.1 J EDG started, but the EDG ouput breaker did NOT close due to loss of DC field flash capability.
D.1 J EDG started and the EDG ouput breaker is closed, but no control power is available to 1 J Bus load breakers.A Incorrect.
Plausible since although the EDG Aux Fuel Oil pump is not needed to start the EDG the candidate who is unfamiliar
with the EDG System may assume this constitutes
a valid reason for the EDG not starting.B Correct.Without the EDG Battery or Battery Charger there is no power available to the start circuits and thus the EDG will not attempt to start despite the presence of automatic start signals.C Incorrect.
Plausible because the candidate may assume that the EDG is capable of starting but that DC for field flash is unavailable.
While the later part is true, as discussed above the EDG will not attempt to start based on the total loss of DC support.D Correct.Plausible because the candidate may assume that the EDG is capable of starting and obtaining required voltage and frequency.
The candidate who is unfamiliar
with DC control power to the ESF busses may conclude that this is a logical reason for none of the ESF equipment to be loaded.The control power to 1 J Bus is from DC Bus 1-111.Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the effect that a loss or malfunction
of the ED/G system will have on the following:
ESFAS controlled
or actuated systems Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 4.2 EDG LP/SD (Not a good reference)
Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 6310 (Partial)10 CFR Part 55 Content: 41.7 Comments: KA Match: Item evaluates malfunction
of EDG based on multiple control power failures, and the resulting effect on the sequencer, which implies effect on the systems controlled
by the sequencer MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 612008 1.00 Version:0I23456789
Answer:BDCCC B-BCAA Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 49.065 AK3.03 022IBANKINORTH
ANNAILOWERJIROINORTH
ANNAl61200S/
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 describes the reason forthisaction?
A.To avoid a High PZR Pressure reactor trip due to closure of all main steam trip valves.B.To avoid a Lo-Lo SG level reactor trip due to closure of all main steam trip valves.To avoid a High Steam Flow safety injection due to closure of a single main steam trip valve.D.To avoid a High Steam Line Delta P safety injection due to closure of a single main steam trip valve.A Incorrect.
Plausible because RCS pressure would rise significantly
on closure of all MSTVs at 100%power.8 Incorrect.
Plausible because if MSTVs close, the SGs would shrink and reach the low level trip setpoint.C Correct.If one MSTV drifts closed (at 100%power),a high steam flow and 10 SG presssure would occur on the other 2 SGs (as steam load does not change), causing a safety injection actuation.
D Incorrect.
The high steam flow wllo SG pressure SI would occur prior to steam line DP SI due to the ratesensitivenature
of the pressure component of the logic.Monday, June 30, 2008 3:34:37 PM 97
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the reasons for the following responses as they apply to the Loss of Instrument
Air:Knowing
effects on plant operation of isolating certain equipment from instrument
air Question Number: Tier: Group: 1 1 Importance
Rating: 2.9 Technical Reference:
AP-28, AP LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 11662 Question History: 10 CFR Part 55 Content: 41.10 Comments: KA is matched because it evaluates knowledge of the effect of losing air to an MSIV, and the safety system actuation that will occur.NORTH ANNA BANK LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: North Anna Bank item with significant
editorial changes MCS Time: I Points: 1.00 Version:0I23456789
Answer:CB A B DBDDDB Scramble Range:A-D Source If Bank: NORTH ANNA Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:37 PM 98
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 50.071 A2.02 082lNEW/IIllGHERlIROINORTH
ANNAl612008/
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?A.1-GW-FCV-1
01, WGDT to Process Vent, should be placed in MANUAL and adjusted to control flow rate at 290+/-5 SCFM.B.1-GW-FCV-1
01, WGDT to Process Vent, should be placed in AUTOMATIC and adjusted to control flow rate at 290+/-5 SCFM.C.1-GW-FCV-1
01, WGDT to Process Vent, should be placed in MANUAL and adjusted to control flow rate at less than 3 SCFM.1-GW-FCV-101, WGDT to Process Vent, should be placed in AUTOMATIC and adjusted to control flow rate at less than 3 SCFM.A Incorrect.
Preferred mode of operation is AUTOMATIC, and maximum indicated flow rate is 3 SCFM;Plausible if operator believes MANUAL control is preferred for radioactive
releases, or if operator confuses the normal Process Vent flow rate with the WGDT release flow rate.B Incorrect.
Maximum indicated flow rate is 3 SCFM;Plausible if operator confuses the normal Process Vent flow rate with the WGDT release flow rate.C Incorrect.
Preferred mode of operation is AUTOMATIC;
Plausible if operator believes MANUAL control is preferred for radioactive
releases.o Correct.0-OP-23.2 stipulates
a flow rate of<3 SCFM and operating 1-GW-FCV-101
in AUTOMATIC;
Operation of 1-GW-FCV-101
in manual is only permitted with permission
from the SRO based on Commitment, P&L, and procedure body, thus AUTOMATIC is clearly preferred.
Monday, June 30, 2008 3:34:37 PM 99
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to (a)predict the impacts of the following malfunctions
or operations
on the Waste Gas Disposal System;and (b)based on those predictions, use procedures
to correct, control, or mitigate the consequences
of those malfunctions
or operations:
Use of waste gas release monitors, radiation, gas flow rate, and totalizer Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 2 3.3 0-OP-23.2, Gaseous Waste LP Proposed references
to be provided to applicants
during examination:
Learning Objective:
Question History: 10 CFR Part 55 Content: Comments: U 4160 MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 612008 1.00 Version:0123456789
Answer: DAAA CDDCCB Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 51.073 Al.OI OOIIBANKINORTH
ANNAILOWERlIROINORTH
ANNAl6/20081YES
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 will trip.B.Both units'vacuum pumps will trip;discharge valves remain open.Both units'vacuum pump discharge valves will automatically
close.D.ONLY the unit 1 vacuum pump discharge valve will automatically
close.A Incorrect.
Both units'vacuum pump discharge valves will close and pumps will then trip.Plausible because the alarm is on Unit1.B Incorrect.
Discharge valves will close.Plausible because the vacuum pump tripping would stop the discharge.
C Correct.Discharge valves for both units vacuum pumps will close.D Incorrect.
Condition affects both Units (See A).Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)associated
with operating the PRM system controls including:
Radiation levels Question Number: Tier: Group: 2 1 Importance
Rating: 3.2 Technical Reference:
NCRODP-46-NA
Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 17679 Question History: NA 5164 10 CFR Part 55 Content: 41.11 oI2 3456789 CDBDCBC ACB Scramble Range:A-D Source If Bank: NORTH ANNA Difficulty
Level: Plant: NORTH ANNA Previous NRC?: YES BANK LOWER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: item evaluates process radiation monitoring
controls for securing potential discharge in progress.MCS Time: I Points: 1.00 Version: Answer: Monday, June 30,20083:34:37
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 52.073 KS.02 065JMODIFIEDIHARRIS
2003ILOWERlIROINORTH
ANNN61200S1
Given the following:
- Following a load reduction, 1-CH-RM-128, Unit 1 Reactor Coolant Letdown Monitor indication
is rising.*Area Surveys 5 feet from a letdown piping hot spot indicate 10 mREM/hr.*An operator must hang a Tagout on a valve that is located 10 feet from the hotspot.What is the dose rate in the area where the operator will be hanging the Tagout?(Assume the hot spot is a point source)A.1 mRem/hr2.5 mRem/hr C.5 mRem/hr D.7.5 mRem/hr A Incorrect.
Mathematical
error would have to be introduced
to arrive at this value but plausible because it is within range and closest to the correct answer.B Correct.Twice the distance is 1/4 the dose rate.C Incorrect but plausible if the applicant fails to square the distance to arrive at dose rate.D Incorrect but plausible if the applicant takes the dose rate and subtracts it from the current dose rate.Monday, June 30, 2008 3:34:37 PM 103
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 1508 RO ONLY Knowledge of the operational
implications
as they apply to concepts as they apply to the PRM system: Radiation intensity changes with source distance Question Number: Tier: 2 Group: 1 Importance
Rating: 2.5 Technical Reference:
Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: Modified from Harris 2003 exam.Developed by others 10 CFR Part 55 Content: 43.11 NORTH ANNA oI2 3456789BCBBBBCCAC
Scramble Range:A-D Source If Bank: HARRIS 2003 Difficulty
Level: Plant: Previous NRC?: Version:
Answer: 1.00 Points: MODIFIED LOWER RO 612008 Comments: KA Match: The item intends to evaluate a situation in which an operator must be aware of changing dose rates and the relationship
between distance and dose rate from a radioactive
source MCS Time: Source: Cognitive Level:.Job Position: Date: Monday, June 30, 2008 3:34:38 PM 104
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 53.076 A 1.02 067INEW/IHIGHERlIROINORTH
ANNA/6/2008/
Given the following:
- Unit 1 is at 100%power.*Computer alarms are received on several components
cooled by the Bearing Cooling System.*Subsequently, the following alarms are received 90 seconds apart:*1 A-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 initialactionrequired?
A.Place Bearing Cooling in Lake-to-Lake Mode and verify the operation of the Circ Water System to ensure cooling requirements
are met.Start available Bearing Cooling Tower Fans or shift fans to high speed;verify Bearing Cooling temperatures
are decreasing.
C.Verify Generator Hydrogen temperature
is above the alarm setpoint and initiate a plant load reduction until the alarm is clear.D.Bypass 1-BC-TCV-104, Generator Hydrogen Cooler TCV, to lower hydrogen temperature.
If temperature
exceeds the limit, trip the reactor.A Incorrect.
Lake to Lake mode may be initiated after evaluation
and after attempting
to start all fans;therefore, plausible because it may be performed.
B Correct.AR for basin temperture
HI is confirmed by annunciator
for Hydrogen temperature
so the initial response would be to maximize system cooling and assess if additional
cooling is adequate to control system supply temperature.
C Incorrect.
Verify temperature
but for the Generator Hydrogen cooler, would attempt to bypass the TCV before anything else.Generator Hydrogen Cooler is a priority component in this situation.
D Incorrect.
Would bypass the TCV if the BC fans did not solve the problem, but would reduce load instead of trip the reactor if temperature
exceeded the limit.Monday, June 30, 2008 3:34:38 PM 105
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)associated
with operating the SWS controls including:
Reactor and turbine building closed cooling water temperatures.
Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 1 2.6 1T-C1, 1A-F4, 1-AP-19 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 11413 10 CFR Part 55 Content: 41.10 Comments: KA Match: Facility has a secondary system called Bearing Cooling that serves the same function as the Service Water system at other facilities.
KA is met because the item requires operating the system controls to prevent exceeding temperature
limits MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW HIGHER RO 612008 1.00 Version:0I23456789
Answer: BCDBA ADDAB Scramble Range:A-D Source If Banle Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:38 PM 106
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 54.076 AK2.01 032INEW//LOWERlIROINORTH
ANNA/6/2008/
Given the following:*A Turbine runback occurred 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago on Unit 1.*The unit is stable at 55%power.*Chemistry sample indicates that RCS activity has increased significantly.
Which ONE of the following radiation monitors provides the primary confirmation
of the Chemistry sample results?A.SG and Main Steam N-16 monitorsReactor Coolant Letdown Radiation monitor C.Auxiliary Building and Vent Stack Radiation monitors D.Containment
Particulate
and Gaseous Radiation monitors A Incorrect.
High N-16 activity would show as a secondary or backup indication
of high RCS activity where SG Tube Leakage is occurring.
These detectors are not sensitive to RCS Activity changes.Plausible because it is logical that an increase in activity would show an increase on the monitor.B Correct.The letdown line monitor is the primary confirmation
that RCS activity has increased.
C Incorrect.
Monitors are checked in AP-5 to verify that no release is occurring if the Letdown Monitor is in alarm.D Incorrect.
RCS activity would provide elevated reading in containment
for conditions
where a small RCS leak is occurring, but not primary indication
for fuel failure/RCS
activity increase.All distractors
plausible because a high RCS activity could result in an increased indication
on the given monitors depended on plant conditions (e.g.RCS leakage, SGTL, CVCS leakage outside CNTMT).Monday, June 30, 2008 3:34:38 PM 107
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the interrelations
between the High Reactor Coolant Activity and the following:
Process radiation monitors Question Number: Tier: Group: 1 2 Importance
Rating: 2.6 Technical Reference:
1-AP-5, Att.8 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 11666 Question History: 10 CFR Part 55 Content: 55.41.12 Scramble Range:A-D NORTH ANNA NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item directly evaluates KA topic by matching the plant condition of high RCS activity based on Chemistry sample with the high rad alarms caused by the Letdown Rad Monitor MCS Time: I Points: 1.00 Version:0I23456789
Answer: B CAABDAABA Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30,20083:34:38
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 55.077 AAl.Ol 024INEW//LOWERlIROINORTH
ANNN61200S1
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
and the condition that requires the offsite power source to be declared inoperable?
A.Maintain voltage regulators
in AUTO;grid voltage increases to 536 kV B.Place voltage regulators
in MANUAL;grid voltage increases to 536 kV C,.-Maintain voltage regulators
in AUTO;grid voltage decreases to 504 kV D.Place voltage regulators
in MANUAL;grid voltage decreases to 504 kV A Incorrect.
Plausible because 536 kV is above the procedural
limit of 535 kV, however the procedure directs EVALUATION
of the offsite source against GDC 17 and continued operability, but does not require the crew to declare it inoperable.
B Incorrect.
Plausible same as A, and VR is not placed in manual.Note in procedure says to leave in AUTO because VR problems have minimal effect.Manual is logical when voltage problems exist.C Correct.Conditions
do not warrant placing VR in manual and 504 kV is the threshold for declaring offsite sources inoperable.
D Incorrect.
Plausible because voltage is correct, and placing in manual is logical when there are voltage problems..Monday, June 30, 2008 3:34:38 PM 109
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances:
Grid frequency and voltage Question Number: Tier: Group: 1 1 Importance
Rating: Technical Reference:
3.6 O-AP-8 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 9364 Question History: 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA o123456789 CDDCABBBAB
Source If Bank: Difficulty
Level: Plant: Previous NRC?: NEW LOWER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match because the item evluates control of voltage (auto or manual)as well as monitoring
voltage for LOW VOLT conditions
MCS Time: 1 Points: 1.00 Version: Answer: Monday, June 30, 2008 3:34:38 PM 110
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 56.078 A4.01 003IBANKINORTH
ANNAILOWERlIROINORTH
ANNA/612008/
Which ONE (1)of the following describes the operation of Instrument
Air Compressor
11-IA-C-1" when it is placed in AUTO?A.Compressor
will start and load when pressure drops to 103 psig.Compressor
will unload and shut down when pressure increases to 109 psig.B.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.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 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.A Incorrect Plausible because it is a description
of howtheService
Air Compressor
will operate in AUTO, with IA setpoints.
B Incorrect.
Plausible because the Service Air Compressor
will run in MANUAL in this manner, but IA setpoints used.C Correct.In AUTO, the lAC will start when pressure is reduced to 98 psig, and unload when pressure reaches 106 psig.D Incorrect.
Plausble because the correct setpoints are used, but in AUTO the compressor
would shut down after 15 minutes running unloaded.Monday, June 30, 2008 3:34:38 PM 111
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to manually operate and/or monitor in the control room: Pressure gauges Question Number: Tier: Group: 2 1 Importance
Rating: 3.1 Technical Reference:
Compressed
Air LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 4271 Question History: 10 CFR Part 55 Content: 41.5 NORTH ANNA BANK LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates pressure setpoints for operation of air compressors, which are the pressures that would be seen if an applicant was monitoring
the pressure gauges MCS Time: 1 Points: 1.00 Version:0123456789
Answer:CC DADBDBCB Scramble Range:A-D Source If Bailie NORTH ANNA Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:38 PM 112
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 57.078 K4.03 068INEW//LOWERlIROINORTH
ANNA/6/2008/
Instrument
Air Compressor
1-IA-C-1 has been running loaded for the past 15 minutes.Which ONE of the following choices contains ONLY alarms that will result in a trip of the Air Compressor?Low Oil Pressure AND CoolingSystemFault
caused by low cooling system DP B.High Discharge Pressure AND Cooling System Fault caused by low cooling system DP C.High Temperature
HP Outlet AND Cooling System Fault caused by high pressure on surge line D.High Oil Temperature
AND Cooling System Fault caused by high pressure on surge line A Correct.A Cooling System Fault alarm will be received either on low DP or on high surge line presure (SW leak)The low DP will trip the compressor
but the high surge line pressure will not.8 Incorrect.
High discharge pressure does not trip the compressor, but does cause an alarm.Plausible because most alarms do result in compressor
trip.C Incorrect.
See A for description
of compressor
trip on low DP only for Cooling system Fault.The first alarm listed will trip the compressor.
D Incorrect.
See A and C.The first alarm listed will trip the compressor.
Monday, June 30, 2008 3:34:38 PM 113
QUESTIONSREPORT
for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of lAS design feature(s)
and/or interlock(s)
which provide for the following:
Securing of SAS upon loss of cooling water Question Number: Tier: Group: 2 1 Importance
Rating: 3.1 Technical Reference:
Compressed
Air LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U4272 Question History: 10 CFR Part 55 Content: 41.7 Scramble Range:A-D NORTH ANNA oI23456789 ACDCAADBAA
Source If Bank: Difficulty
Level: Plant: Previous NRC?: NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match because the item evaluates knowledge of an interlock to trip the air compressor
based upon low cooling water flow.MCS Time: I Points: 1.00 Version: Answer: Monday, June 30, 2008 3:34:38 PM 114
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 58.079 Kl.Ol OOllMODIFIED/IHIGHERJIROINORTH
ANNN6120081
Given the following:*A loss of Instrument
Air is occurring on Unit 1.*Instrument
Air pressure is 88 psig and dropping slowly.*The actions of 1-AP-28, Loss of Instrument
Air, are being performed.
Which ONE (1)of the following describes the Instrument
Air System alignment and the action to be taken based on the system pressure?A.All available Instrument
and Service Air Compressors
running;Verify Instrument
Air supplied to Containment
by verifying open 1-IA-TV-102A
and 1-IA-TV-1028, Containment
Instrument
Air Trip Valves.All available Instrument
and Service Air Compressors
running;Isolate Instrument
Air to Containment
by closing 1-IA-TV-1 02A or 1-IA-TV-1 028, Containment
Instrument
Air Trip Valves.C.All Service Air Compressors
running;Instrument
Air Compressors
either running or in standby;Verify Instrument
Air supplied to Containment
by verifying open 1-IA-TV-1 02A and 1-IA-TV-1 028, Containment
Instrument
Air Trip Valves.D.All Service Air Compressors
running;Instrument
Air Compressors
either running or in standby;Isolate Instrument
Air to Containment
by closing 1-IA-TV-102A
or 1-IA-TV-1028, Containment
Instrument
Air Trip Valves.A Incorrect.
Immediate action is to start all available Service Air, Instrument
Air, and Containment
Instrument
Air Compressors.
No other immediate actions.Plausible but at 94 psig, the procedure directs isolation of the Containment
Air Header to try and identify where the leak is.8 Correct.Immediate action is to start all available Service Air, Instrument
Air, and Containment
Instrument
Air Compressors.
No other immediate actions.At 94 psig, the procedure directs isolation of the Containment
Air Header to try and identify where the leak is.C Incorrect.
Plausible because Service Air Compressors
are normal supply to Instrument
Air, and Instrument
Air Compressors
are only used for backup.Also, Containment
Air trip valves are normally open to supply air to Containment.
D Incorrect.
Plausible because Service Air Compressors
are normal supply to Instrument
Air, and Instrument
Air Compressors
are only used for backup.Also, Containment
Air will be split at 94 psig.Monday, June 30, 2008 3:34:38 PM 115
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the physical connections
and/or cause-effect
relationships
between the SAS and the following lAS Question Number: Tier: Group: Importance
Rating: Technical Reference:
2 2 3.0 1-AP-28, NCRODp*17 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 11662 10 CFR Part 55 Content: 41.10 Comments: KA Match: Item evaluates connections
between Service Air, Instrument
Air, and Containment
Instrument
Air diu ring an abnormal event.Service and Instrument
Air systems are always cross-tied;
Containment
Air may be automatically
or manually isolated Modified because air pressure was added to stem, and status of Containment
Air was also added to options.Correct answer changed based on modifications
MCS Time: Source: Cognitive Level: Job Position: Date: Points: MODIFIED mGHER RO 612008 1.00 Version:0123456789
Answer: BCDDCCDBDA Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:38 PM 116
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 1508 RO ONLY 59.103 A3.01 070INEW//LOWERlIROINORTH
ANNN61200S1
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 nowslowlydecreasing.
- The crew is performing
1-E-0, Reactor Trip or Safety Injection.
- The RO is performing
Attachment
5, Verification
of Phase A Isolation.
- The following valves are identified
as OPEN:*1-CH-MOV-1115B, RWST To Charging Pumps Isolation*1-CH-MOV-1289B, Normal Charging Line Isolation*1-SV-TV-100A, MSR Vent to First Point Heater*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-CH-MOV-1115B1-CH-MOV-1289B
C.1-SV-TV-100A
D.1-SW-MOV-108A
A Incorrect.
Valve is normally closed but will open on SI.Plausible because it is normally closed and the applicant must determine from conditions
and procedure step that SI is actuated, and that VCT valves with same numbers will be open during normal operation (Same designator, different letter).B Correct.Normal Charging isolates on SI, but plausible that it should be open, because a loss of inventory has occurred, and Charging provides makeup.C Incorrect.
Valve must be closed manually as part of Attachment
5, but does not receive an auto close signal, and not required for safety related function.TheMSRs are realigned to the condenser manually.D Incorrect.
Valve will close on CDA (CIB)Conditions
do not exist for CIB.Plausible because they do get a close signal on Hi-Hi containment
pressure.Monday, June 30,20083:34:38
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to monitor automatic operation of the contain-ment
system, including:
Containment
isolation Question Number: Tier: Group: 2 1 Importance
Rating: 3.9 Technical Reference:
1-E-O, Attachment
5 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 12021 Question History: 10 CFR Part 55 Content: 41.7 Scramble Range:A-D NORTH ANNA aI23456789 BDCADCCDDC
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Version: Answer: 1.00 NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates knowledge of the components
that are requiredtoreposition
on containment
isolation Phase A.Each option has a unique actuation or manipulation
to ensure that each is plausible.
MCS Time: I Points: Monday, June 30, 2008 3:34:39 PM 118
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 60.E03 EA1.2 036INEW//HIGHER//RO/NORTH
ANNA/6/2008/
Given the following:*A LOCA has occurred on Unit1.*The crew is performing
1-ES-1.2, Post LOCA Cooldown and Depressurization.
- During the SI flow reduction sequence, the following conditions
exist:*1C RCP is running.*Two Charging Pumps are running.*RCS pressure is 1100 psig and stable.*RCS Subcooling
based on Core Exit TCs is 320F*Pressurizer
level is 44%.*Containment
pressure is 17.9 psia.Which ONE of the following describes the action required for the SI flow reduction sequence in accordance
with 1-ES-1.2?A.RCS subcooling
is adequate to prevent the RCS from reaching saturation
conditions
when one Charging Pump is stopped;maintain RCS temperature
stable while stopping one Charging Pump.B.RCS subcooling
is adequate to prevent the RCS from reaching saturation
conditions
when one Charging Pump is stopped;continue the RCS cooldown while stopping one Charging Pump.C.RCS subcooling
is NOT adequate to prevent the RCS from reaching saturation
conditions
when one Charging Pump is stopped;one Charging Pump may be stopped ONLY IF at least one Low Head SI pump is running..RCS subcooling
is NOT adequate to prevent the RCS from reaching saturation
conditions
when one Charging Pump is stopped;Charging Pumps must remain running with flow aligned to the BIT until RCS subcooling
is sufficient
to stop a Charging Pump.Monday, June 30, 2008 3:34:39 PM 119
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 041508 RO ONLY A Incorrect.
RCS subcooling
is sufficient
for normal EOP conditions
(>25 Degrees F)but not sufficient
<<50 Degrees F)for Sl flow reduction.
Therefore, this option is plausible.
Maintaining
temperature (plant conditions)
stable is a logical action to perform while stopping a pump that will change RCS subcooling.
B Incorrect.
See A above, and also the action is correct for the conditions
given if an applicant chose the first part of this option.C Incorrect.
Plausible because this is the RNO action for the step in question.If Hot Leg temperatures
were below 345 Degrees F, this would be a correct option.D Correct.ERG Rev.2 Basis for SI reduction sequence.With a leak in progress additional
subcooling
is required to ensure subcooling
does not decrease to SI reinitiation
criteria when injection flow is reduced.The increased subcooling
required is intended to ensure adequate subcooling
when new equilibrium
conditions
establish after a Charging pump is stopped.Ability to operate and/or monitor the following as they apply to the (LOCA Cooldown and Depressurization)
Operating behavior characteristics
of the facility.Question Number: Tier: Group: 1 2 Importance
Rating: 3.7 Technical Reference:
E5-1.2 and SD Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 12208 Question History: 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA NEW HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item
knowledge of the operating behavior characteristics
of the facility in order to eliminate distractors, as well as determine correct answer.The applicant must understand
subcooling
requirements
in an abnormal EOP arrangement, and understand
the 51 flow reduction process related to stopping a Charging Pump in order to correctly answer.MCS Time: 1 Points: 1.00 Version:0123456789
Answer: DDDB BACDDC Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30,20083:34:39
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 61.E05 EK3.4 023lNEW/IHIGHERJIROINORTH
ANNN6/20081
Initial Conditions:
- Reactor trip on Unit1.*Safety Injection and Main Steam Line Isolation have actuated.*1B SG pressure is 220 psig and lowering due to a stuck open safety valve.*1A and1C SG pressures are 700 psig and stable.*RCS pressure 1600 psig and stable.Current conditions:
- All AFW flow has been lost.*1A and1C SG Wide Range levels are 30%and lowering.*1B SG Wide Range level, indicates 0%.*RCS pressure is 1750 psig and rising.*All actions of 1-E-2, Faulted SG Isolation, have been performed.
- The crew has just transitioned
to 1-FR-H.1, Loss of Secondary Heat Sink.Which ONE of the following describes the strategy for recovery of Heat Sink in accordance
with 1-FR-H.1, and the reason for the strategy?A.Establish AFW flow to ANY SG;establishing
Heat Sink takes priority over any previous EOP action.Establish AFW flow to1A OR1C SG;1B SG should remain isolated to prevent potential SG tube damage.C.Establish bleed and feed and if AFW becomes available, then establish AFW to ANY SG;establishing
Heat Sink takes priority over any previous EOP action.D.Establish bleed and feed and if AFW becomes available, then establish AFW to 1A OR1C SG;1B SG should remain isolated to prevent potential SG tube damage.Monday, June 30,20083:34:39
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 1508 RO ONLY A Incorrect.
Actions of FRPs do take precedence
over other procedures, but a caution prior to step 1 of FR-H.1 requires use of intact SGs for initiation
of feed instead of faulted SGs.Plausible because a loss of heat sink is in progress.8 Correct.The caution referenced
in FR-H.1 is standard throughout
the EOP network and is intended to alert the operator to the potential for damage as well as the difficulty
involved in attempting
to control RCS temperature
with a faulted SG;either condition can result in adverse consequences
and has the potential to complicate
recovery actions.C Incorrect.
SG WR level is below the adverse value, but above the normal value for initiation
of bleed and feed;therefore, plausible option.Recovery with AFW would follow the caution to leave the faulted SG isolated.D Incorrect and plausible same as C.Actions for restoration
of AFW are correct.Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink)RO or SRO function as a witnin the control room team as appropriate
to the assigned position, in such a way that procedures
are adhered to and the limitations
in the facilities
license and amendments
are not violated.Question Number: Tier: Group: 1 1 Importance
Rating: 3.7 Technical Reference:
FR-H.1 and background
doc Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 11276 Question History: 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA 0123456789
BCBACBDAAD
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Version: Answer: 1.00 Points: NEW HIGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: The item evaluates plant conditions
where an applicant must observe a caution in order to perform the correct action during a loss of feedwater.
The applicant is presented with 2 plausible options for initial action, as well as 2 plausible options for reasons, both contained in EOPs MCS Time: Monday, June 30, 2008 3:34:39 PM 122
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 62.E09 EA2.l 037INEW//HIGHERJIROINORTH
ANNA/6/2008/
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-0.1, 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?ES-0.2A, Natural Circulation
Cooldown with CRDM Fans;25 degrees F/Hr.B.ES-0.2A, Natural Circulation
Cooldown with CRDM Fans;15 degrees F/Hr.C.ES-0.2B, NaturalCirculationCooldown
without CRDM Fans;25 degrees F/Hr.D.ES-0.2B, Natural Circulation
Cooldown without CRDM Fans;15 degrees F/Hr.A Correct.With loss of off-site power, power is still available to operate CRDM cooling fans, so the crew will use ES-0.2A for the cooldown.Specified cooldown rate is correct.B Incorrect.
The procedure selected is correct, but the cooldown rate is incorrect but plausible because it is associated
with selection of ES-0.2B for the cooldown.C Incorrect.
Incorrect procedure;
ES-0.2B is performed after the first 5 steps of ES-0.2A are completed, and ONLY if less than 3 CRDM fans are in operation.
In this case, 3 CRDM fans are operating/available.
The candidate who is unfamiliar
with CRDM fan power supplies may assume they are unavailable
is they are not Safety Related loads.The cooldown rate is for use of ES-0.2A, but plausible since candidate who is unfamiliar
with procedure difference
may default to the 25 degree per hour value.D Incorrect.
Incorrect procedure as in C, but cooldown rate is correct if ES-0.2B were the correct procedure to use.Monday, June 30, 2008 3:34:39 PM 123
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to determine interpret the following as they apply to the (Natural Circulation
Operations)
Facility conditions
and selection of appropriate
procedures
during abnormal and emergency operations.
Question Number: Tier: Group: 1 2 Importance
Rating: 3.1 Technical Reference:
ES-0.2A, ES-0.2B Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 12030 Question History: 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA NEW mGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluates facility conditions
where a Natural Circulation
Cool down is required, and provides the applicant with 2 plausible choices of procedure based upon abnormal plant alignment, and 2 plausible choices for RCS cool down rate MCS Time: 1 Points: 1.00 Version:0123 456789 Answer: ADCCCB ADAC Source If Banle Difficulty
Level: Plant: Previous NRC?: Monday, June 30,20083:34:39
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 63.E!2 EK2.!OS3IMODIFIED//LOWERlIROINORTH
ANNAl61200S1
Upon entry into 1-ECA-2.1, Uncontrolled
Depressurization
of All Steam Generators, the crew determines
that RCS cool down rate is 10goF/Hr.Which ONE (1)of the following describes how the crew is directed to control AFW flow?A.Total flow is maintained
>340 gpm until ALL SG narrow range levels are>11%.B.Total flow is maintained
>340 gpm until ANY SG narrow range level is>11%.C.Flow is reduced to 100 gpm to each SG, and narrow range level is controlled
at greater than 11%.Flow is reduced to 100 gpm to each SG, and narrow range level is controlled
at less than 50%.A Incorrect but plausible because it is similar to the action contained in E-O, and also the level that all SGs are maintained
in EOPs.Also, applicant must understand
that AFW requirements
change based upon RCS cooldown rate in ECA-2.1.B Incorrect but plausible because it is the normal level control in EOPs and is normally required to avoid transition
and implementation
of FR-H.1.C Incorrect but plausible because the flow rate is correct.The level value is incorrect, the applicant must understand
that level may not be maintained
adequately
when throttling
AFW due to RCS cooldown for different sized breaks, and that FR-H.1 will not be implemented
under these circumstances
as specific allowance is contained in the procedure to address this situation.
D Correct.Above 100 degrees F RCS cooldown rates, AFW is throttled to minimum.The criteria for raising AFW flow is hot leg temperature
increasing, not going below minimum SG level.Monday, June 30, 20083:34:39
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the interrelations
between the (Uncontrolled
Depressurization
of all Steam Generators)
and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.Question Number: Tier: Group: 1 1 Importance
Rating: 3.4 Technical Reference:
ECA-2.1, E-O Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 13843 Question History: 10 CFR Part 55 Content: 41.10 Comments: KA Match: Item evaluates function and control (as well as manual operation)
of AFW system for a condition where an excessive RCS cooldown rate has occurred due to multiple SG depressurization.
Original Scramble Range:A-D NORTH ANNA MODIFIED LOWER RO 612008 Source: Cognitive Level: Job Position: Date: Have developed similar with different distractors.
None found previous NRC.provided from VC Summer previous AUDIT exam MCS Time: 1 Points: 1.00 Version:0123456789
Answer: DCDBDDBBAC
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30,20083:34:39
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 64.E 15 EK2.I 034IBANKINORTH
ANNA 2006IHIGHERJ/RO/NORTH
ANNAl6/2008NES
Given the following:*A Steam Break has occurred inside Unit 1 Containment.
- SI, Main Steam Line Isolation, Phase A, CDA and Phase B have automatically
actuated.*The crew has completed 1-E-2, Faulted SG Isolation.
- An ORANGE condition exists on the Containment
CSF Status Tree.*The crew transitions
to FR-Z.2, Containment
Flooding.Which ONE of the following describes the source of leakage that will require action to isolate?A.Chilled WaterService Water C.Primary Grade Water D.Component Cooling Water A Incorrect.
Chilled Water will be isolated during CDA, so it would not be causing the level change.B Correct.With CDA actuated, RS Heat Exchangers
are supplied with Service Water flow.C Incorrect.
Primary Grade Water will be isolated in the current plant condition.
D Incorrect.
Component Cooling water is isolated on Phase B caused by Hi-Hi Containment
pressure (CDA).All of the above systems are plausible because they are identified
as sources by FR-Z.2 Monday, June 30, 2008 3:34:39 PM 127
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the interrelations
between the (Containment
Flooding)and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.Question Number: Tier: Group: 1 2 Importance
Rating: 2.8 Technical Reference:
FR-Z.2, Chilled Water LP, CC LP, PG LP, SW LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 13869 Question History: re-ordered (see 2006 Retake;Editorially
modified;stem changed, distractors
original)10 CFR Part 55 Content: 41.5,7 0123456789
BDDBDAAACD
Scramble Range:A-D Source If Bank: NORTH ANNA 2006 Difficulty
Level: Plant: NORTH ANNA Previous NRC?: YES Version: Answer: 1.00 Points: BANK HIGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: This item evaluates the function of safety systems as they apply to FR-Z.2 because ESF actuations
occur based upon Containment
pressure.The applicant must determine which systems are servicing Containment
in the current plant condition, to be able to answer the question.MCS Time: Monday, June 30, 2008 3:34:39 PM 128
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 65.E16 EK3.1 035IBANKlILOWERlIROINORTH
ANNN61200S1
A Small Break LOCA has occured on Unit 1.The following plant conditions
exist:*Complications
in recovery have resulted in some core damage.*Containment
Pressure peaked at 13 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 the actions provided by 1-FR-Z-3 to mitigate the condition?
A.Evaluate starting Outside Recirc Spray pumps and injecting the CAT.B.Evaluate starting Inside Recirc Spray pumps and injecting the CAT.Evaluate placing Containment
Atmosphere
Filtration
System in service.D.Evaluate venting Containment
via the Iodine Filter banks.A Incorrect.
Plausible based on the abnormal Containment
conditions.
Both cold spray water and the NAOH solution in the CAT help maintain Iodine in solution, thus the candidate who is unfamilliar
with FR-Z.3 may default to this as a logical solution.B incorrect.
Plausible based on the abnormal Containment
conditions.
Both cold spray water and the NAOH solution in the CAT help maintain Iodine in solution, thus the candidate who is unfamilliar
with FR-Z.3 may default to this as a logical solution.Since there are obvious differences
with ISRS and OSRS, candidate may assume one is preferential
to the other for the conditions
given in the, stem.C Correct.As described in FR-Z.3 ERG Background
Document, use of spray is not appropriate
for the given conditions, thus Containment
Atmospheric
Filtration
System is the only viable option.D Incorrect.
Plausible;
since the Iodine filters do remove Iodine the candidate who is unfamilliar
with FR-Z.3 may default to this as a logical solution.Monday, June 30, 2008 3:34:39 PM 129
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Knowledge of the reasons for the following responses as they apply to the (High Containment
Radiation)
Facility operating characteristics
during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity
changes and operating limitations
and reasons for these operating characteristics.
Question Number: Tier: Group: 1 2 Importance
Rating: 2.9 Technical Reference:
FR-l.3, FR-l.3 SD Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 13871 Question History: 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA BANK LOWER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item evaluated reason for elevated radiation levels after a LOCA, as well as action required to mitigate.The reason is based on temperature, as indicated in the KA statement MCS Time: I Points: 1.00 Version:0I23 456789 Answer:CABCDC CCAD Source If Banle Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:39 PM 130
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 66.G2.1.20 084IMODIFIED//LOWERlIROINORTH
ANNAi6/2008/
In Emergency Operating Procedure 1-E-0, 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;the EOP Network is exited B.Decision Making Steps;the EOP Network is exitedContinuous
Action Steps;transition
from 1-E-0 is made D.Decision Making Steps;transition
from 1-E-0 is made A Incorrect.
Asterisk is used for continuous
actions but the requirements
to perform the step end when a transition
from the procedure in effect is made.B Incorrect.
Circled steps are decision making steps and only apply at the time read.C Correct.An asterisk is used for continuous
actions but the requirements
to perform the step end when a transition
from the procedure in effect is made.D Incorrect.
Circled steps are decision making steps and only apply at the time read.Monday, June 30, 2008 3:34:40 PM 131
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Conduct of Operations:
Ability to interpret and execute procedure steps.Question Number: Tier: Group: 3 1 Importance
Rating: 4.6 Technical Reference:
DNAP-0509 Procedure Use, EP LP Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 12039 Question History: Modified from North Anna 2004 Exam, question provided 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA o12 3456789 CABDBDDABA
Source If Bank: Difficulty
Level: Plant: Previous NRC?: MODIFIED LOWER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA is matched because the item evaluates whether the applicant understands
the designators
for steps and how they are applied MCS Time: 1 Points: 1.00 Version: Answer: Monday, June 30, 2008 3:34:40 PM 132
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 67.G2.1.37 086INEW//HIGHERI/RO/NORTH
ANNAl612008/
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.Performing
a blended makeup to the RCS B.Reducing Steam Generator Blowdown Flow Rate C.Raising Letdown temperatureOperating the Steam Driven Aux Feed Pump Turbine A Incorrect.
While this action might be considered
desirable if powerwasclose to 100%, there is no specific requirement
in OP-AP-300 to do so.Plausible because past plant issues with blender components
have led to lighter than desired blended makeups.B Incorrect.
Reducing SG blowdown flow rate will result in actual power lowering.The guideline requires reducing power if blowdown flow is raised, as that would result in actual power rising above indicated power.Plausible because power changes with a change in blowdown flow and the applicant must understand
which way it does change.C Incorrect.
Raising letdown temperature
will actually lower power as the letdown demins will release boron at higher temperatures.
Plausible because changing letdown temperature
does have an effect on reactor power, and the applicant must know which way it will change for a change in temperature.
D Correct.Starting the TDAFW Pump turbine will result in a larger heat removal from RCS, lowering temperature, and causing an increase in reactor power.OP-AP-300 lists starting the TDAFW pump as an evolution requiring power reduction.
Monday, June 30, 2008 3:34:40 PM 133
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Conduct of Operations:
Knowledge of procedures, guidelines, or limitations
associated
with reactivity
management.
Question Number: Tier: Group: 3 1 Importance
Rating: 4.3 Technical Reference:
OP-AP-300 Attachment
2 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 13307 Question History: 10 CFR Part 55 Content: 41.5, 10 Scramble Range:A-D NORTH ANNA NEW HIGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item directly evaluates knowledge of the required topic based on a facility procedure, Reactivity
Management, for operation at 100%power.MCS Time: 1 Points: 1.00 Version:0123456789
Answer: DCBBBB CBDA Source If Banle Difficulty
Level: Plant:
Previous NRC?: Monday, June 30, 2008 3:34:40 PM 134
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 68.G2.1.41 085lNEW/IHIGHERlIROINORTH
ANNN61200S1
Given the following:
Unit 1 is shut down in preparation
for Refueling in accordance
with 1-0P-4.1, Controlling
procedure for Refueling.
In accordance
with 1-0P-4.1, which ONE of the following choices describes (1)the method of filling the Refueling Cavity and (2)which evolution constitutes
the FI RST Core Alteration?
A.(1)Gravity fill from RWST, then LHSI pump (2)Lifting of the Reactor Vessel Upper Internals(1)Gravity fill from RWST, then LHSI pump (2)Control Rod Drive Shaft unlatching
C.(1)LHSI pump ONLY (2)Lifting of the Reactor Vessel Upper Internals D.(1)LHSI pump ONLY (2)Control Rod Drive Shaft unlatching
A Incorrect.
Gravity fill is the method used to fill the cavity if RWST is at normal level.Upper internals lift is considered
a core alteration
however it can not occur until after rod unlatching.
Candidates
who are unfamiliar
with thesequenceof
reactor disassembly
may choose this distractor.
B Correct.Method of filling is correct, as stated above unlatching
is performed before the upper internals are lifted, so it constitutes
the firstcorealteration.
C Incorrect.
LHSI fill is performed after the gravity fill flow rate drops below 1600 GPM.Plausible because it is the method used once gravity fill is no longer effective.
As stated above the upper internals lift follows rod unlatching, but candidates
who are unfamiliar
with the sequence of reactor disassembly
may choose this distractor.
D Incorrect.
LHSI fill is performed after the gravity fill flow rate drops below 1600 GPM.Plausible because it is the method used once gravity fill is no longer effective.
First core alteration
is correct.Monday, June 30, 2008 3:34:40 PM 135
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Conduct of Operations:
Knowledge of the refueling process.Question Number: Tier: Group: 3 1 Importance
Rating: 2.8 Technical Reference:
1-0P-4.1 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 9025 Question History: 10 CFR Part 55 Content: 41.10,43.6
Scramble Range:A-D NORTH ANNA NEW HIGHER RO 612008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: This item directly matches the KA topic because it evaluates actions contained in the refueling process, specifically
the first core alteration
and the method of filling the refueling cavity.Both evolutions
are covered in the controlling
procedure fior refueling MCS Time: 1 Points: 1.00 Version:0123456789
Answer:BDBCDB CCCA Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30,20083:34:40
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 69.G2.2.1 089lNEW/IHIGHERlIROINORTH
ANNAl6120081
Given the following:
- An approach to criticality
is in progress in accordance
with 1-0P-1.7, Unit Startup from Mode 3 to Mode 2 Following Refueling.
- Control Banks are at their estimated critical position.*RCS dilution has been secured.*Criticality
is imminent above the ECC Upper Boron Limit.Which ONE of the following actions is required in accordance
with 1-0P-1.7?A.Wait approximately
20 minutes to ensure mixing of PG water;establish a startup rate below 1 DPM using additional
dilution or Control Bank D withdrawal.
B.Reinitiate
RCS dilution in approximately
200 gallon batches;ensure Control Bank D isabovethe rod insertion limit;when criticality
is declared, establish a startup rate below 1 DPM using additional
dilution or Control Bank D withdrawal.
C.Stop the reactor startup;stabilize reactor power level, and direct Reactor Engineering
to reevaluate
parameters
and values used to calculate the ECC prior to continuing.Insert Control Bank D to 5 steps;manually trip the reactor and verify Shutdown Margin requirements
are met.A Incorrect.
If criticality
is achieved above the upper boron limit, that means that the reactor will be critical significantly
prior to when it is supposed to be.Plausible because this is an infrequently
performed evolution, and it is easy to confuse'above'and'below'as well as'upper'and'lower'boron concentration
limits.Actions are consistent
with normal startup actions.B Incorrect.
This would also be consistent
with normal startup actions.Applicant may confuse'above upper'and'below lower'and believe that a normal startup is in progress.If wording was changed in stem to'slightly below the upper limit'this would be true.C Incorrect.
RE will evaluate the ECC, but reactor would be tripped, not stabilized.
Plausible, because stabilizing
power places the plant in a safe condition with RILs met, as stem describes.
D Correct.See discussion
above and procedure.
Monday, June 30, 2008 3:34:40 PM 137
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Equipment Control: Ability to perform pre-startup
procedures
for the facility, including operating those controls associated
with plant equipment that could affect reactivity.
Question Number: Tier: Group: 3 2 Importance
Rating: 4.5 Technical Reference:
1-0P-1.7 and attachment
3 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 15997 Question History: 10 CFR Part 55 Content: 41.10,5 Scramble Range:A-D NORTH ANNA NEW HIGHER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA is matched because this item evaluates operating controls that could affect reactivity, whether inserting or withdrawing
rods, or initiation
of dilution.Inserting rods to 5 steps and manually tripping the reactor on a premature criticality
mets the intent of this KA MCS Time: I Points: 1.00 Version:0123 456789 Answer: DADDCCCCBB Source If Bank: Difficulty
Level: Plant: Previous NRC?: Monday, June 30, 2008 3:34:40 PM 138
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 70.02.2.39 091IMODIFIED//LOWERlIROINORTH
ANNAl612008INO
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 indications
requires Technical Specification
action within ONE (1)hour?A.RWST temperature
38 degrees F.Containment
air partial pressure 12.9 psia.C.Quadrant Power Tilt Ratio 1.022.D.RCS UNIDENTIFIED
LEAKAGE is 1.20 gpm.A Incorrect.
RWST temperature
requires action within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.Plausible because RWST inoperability
for any reason other than temperature
or boron concentration
requires action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.B Correct.Applicant must determine that the value will exceed the tech spec limit based on the curve under all conditions.
C Incorrect.
QPTR requires action within 30 minutes if it is greater than 1.02, but only applies with the unit>50%power.Plausible because it would require action if power were higher.D Incorrect.
RCS operational
leakage Tech Spec allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore leakage to within limits.Plausible since an operator who is unfamiliar
with Tech Specs may feel that 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is appropriate
based on urgency of the situation.
Monday, June 30,20083:34:40
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Equipment Control: Knowledge of less than one hour technical specification
action statements
for systems.Question Number: Tier: Group: Importance
Rating: Technical Reference:
3 2 3.9 TS 3.6.4 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: U 10698 10 CFR Part 55 Content: 43.2 Comments: MCS Time: Source: Cognitive Level: Job Position: Date: Points: MODIFIED LOWER RO 6/2008 1.00 Version: Answer: o123456789 BACBBADACD
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Scramble Range:A-D NORTH ANNA NO Monday, June 30, 2008 3:34:40 PM 140
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 71.G2.2.7 090lNEW/ILOWERJIROINORTH
ANNN6/20081
Given the following:*A mid-cyclereactorstartup
is planned for Unit1.*NO special tests or evolutions
are required during the startup.In accordance
with OP-AA-106, Infrequently
Conducted or Complex Evolutions, which ONE of the following describes the category of ICCE, and the level of supervision
required for the ICCE?Note: Category II-Tests or Evolutions
That Have the Potential to Degrade Safety Due to the Complexity
or Unpredictably
of the Test or Evolution Category III-Routine Tests or Evolutions
That Are Complex Due to Abnormal Initial Conditions, Concurrent
Tests, or Infrequent
Performance
A.Category II;Shift Manager, OMOC Qualified B.Category II;Department
Manager, presently or previously
SRO licensedCategory III;Shift Manager, OMOC Qualified D.Category III;Department
Manager, presently or previously
SRO licensed A Incorrect.
Category II would be for tests performed during a reactor startup that would degrade or potentially
degrade plant performance.
Plausible because reactor startup-related
tasks are given as examples of Category II ICCEs.8 Incorrect.
Same reason as A and Dept.Mgr would be correct if the ICCE was a category II.C Correct.Reactor startup noted as a category IIIICCE, and SM (OMOC qualified)
must be provided for oversight.
D Incorrect.
Plausible because category is correct, but level of supervision
would be required for category II or I ICCE.Monday, June 30,20083:34:40
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Equipment Control: Knowledge of the process for conducting
special or infrequent
tests.Question Number: Tier: Group: Importance
Rating: Technical Reference:
3 2 2.9 OP-AA-106, section 5.3 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
Question History: 10 CFR Part 55 Content: 41.10 Comments: KA is matched because item directly evaluates knowledge of the process and hierarchy of ICCEs, providing for selection of level as well as required supervision
for an operationally
relevant evolution MCS Time: Source: Cognitive Level: Job Position: Date: Points: NEW LOWER RO 6/2008 1.00 Version:0I23456789
Answer:CCBBDDDCBC
Scramble Range:A-D Source If Bank: Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:40 PM 142
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 72.G2.3.15 095IBANKINORTH
ANNA 6135ILOWERJIROINORTH
ANNAl612008INO
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?A.Verify the fuel pit bridge radiation monitor is operable.B.Verify the fuel building ventilation
exhaust is aligned to the charcoal filter.Place the fuel building radiation automatic interlock key switch in DISABLE.D.Reset the new fuel storage area radiation monitor by pulling and reinserting
fuses.A Incorrect.
SFP bridge monitor does not show indication
of inoperability, supported by HP determination
of radiation levels.Plausible because it is logical to use redundant indication
for a monitor in alarm.B Incorrect.
The Fuel Building Ventilation
system and doors are normally in Configuration
B.High radiation would cause ventilation
alignment to filtered exhaust.Verification
isnotrequired
based on the failure presented, but would be required for an actual high radiation condition lAW AP-30.C Correct.ARP will send the operator to 0-AP-5.1, which will place switch in DISABLE prior to bottled air dump.D I ncorrect.Subsequent
action in attachment
3 will attempt to reset the radiation monitor by pulling and reinserting
fuses.Monday, June 30, 2008 3:34:40 PM 143
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Radiation Control: Knowledge of radiation monitoring
systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring
equipment, etc.Question Number: Tier: Group: 3 3 Importance
Rating: 2.9 Technical Reference:
1 K-D3, 0-AP-5.1 steps 1, 2, and attachment
3 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 10705 Question History: 10 CFR Part 55 Content: 41.11 BANK.LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA match: Item directly evaluates the radiation monitoring
system for the Fuel Handling system by requiring knowledge of actuation based on alarm status, and action required to prevent actuation based upon'the alarm status of a fixed radiation monitor', MCS Time: 1 Points: 1.00 Version:0123456789
Answer: C CADBAAAAC Scramble Range:A-D Source If Bank: NORTH ANNA 6135 Difficulty
Level: Plant: NORTH ANNA Previous NRC?: NO Monday, June 30, 2008 3:34:41 PM 144
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 73.G2.3.4 094INEW//LOWER//RO/NORTH
ANNN6/2008/
Given the following:
- An explosion and fire occurred in the Auxiliary Building.*The fire has been extinguished.
- Process Vents radiation monitor indication
is increasing.
- Auxiliary Building radiation monitor indications
are increasing
..*After the explosion, the Auxiliary Building watchstander
informed the Shift Manager that he was injured and unable to move.The Station Emergency Manager (SEM)is evaluating
dispatching
a team to the Auxiliary Building.Which ONE of the following is CORRECT concerning
the SEM's decision making process?A.The SEM should authorize no more than 10 rem TEDE for each search and rescue individual
to retrieve the injured watchstander.
B.The SEM should authorize no more than 10 rem TEDE combined dose for the search and rescue team to retrieve the injured watchstander.
Cr The SEM should authorize no more than 25 rem TEDE for each search and rescue individual
to retrieve the injured watchstander.
D.The SEM should authorize no more than 25 rem TEDE combined dose for the search and rescue team to retrieve the injured watchstander.
A Incorrect.
Plausible because there is a limit of 10 Rem TEDE, but that limit is applicable
to save valuable equipment or limit off-site releases.B Incorrect.
Plausible;
as stated above the limit of 10 Rem TEDE is applicable
to save valuable equipment or limit off-site releases.Further, since most ALARA practices are concerned with total dose;the candidate who is unfamiliar
with the specific guidance of the EPIP may default to this since with a team of people, allowing each one to get up to 10 rem seems excessive.
C Correct.The limit of 25 Rem TEDE is applicable
for search and rescue, first aid, and (as given in the stem)removal of injured personnel.
Limit is for each individual.
o Incorrect.
The limit of 25 Rem TEDE is applicable
for search and rescue, first aid, and (as given in the stem)removal of injured personnel.
Plausible since most ALARA practices are concerned with total dose;the candidate who is unfamiliar
with the specific guidance of the EPIP may default to this since with a team of people, allowing each one to get up to 25 rem seems excessive.
Monday, June 30, 20083:34:41
QUESTIONS REPORT for NORTH ANNA NRC exam-RavO 04 15 08 RO ONLY Knowledge of radiation exposure limits under normal or emergency conditions
Question Number: Tier: Group: 3 3 Importance
Rating: 3.2 Technical Reference:
VPAP 2101 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
13583 Question History: This is called a Bank question, although it is written new.Items are in the bank containing
similar attributes
and context 10 CFR Part 55 Content: 41.12 Scramble Range: A-D NORTH ANNA o12 3456789 CADDABCBCA
Source If Bank: Difficulty
Level: Plant: Previous NRC?: Version:
Answer: 1.00 Points: NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: Item directly evaluates administrative
exposure limits, which is the topic addressed by the KA MCS Time: Monday, June 30, 2008 3:34:41 PM 146
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 74.G2.4.32 097INEW//LOWERJ/RO/NORTH
ANNN6/2008/
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*Unit 1 determines
that the control room annunciators
have stopped functioning.
- The crew enters 1-AP-6, Loss of Main Control Room Annunciators.
Which ONE of the following actions is required in accordance
with 1-AP-6 if the Unit 1 Annunciators
are not immediately
restored?A.Initiate a controlled
plant shutdowntoMode 3;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.Maintain reactor power stable;log AFD every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.C.Initiate a controlled
plant shutdown to Mode 3;log AFD hourly.Maintain reactor power stable;log AFD hourly.A Incorrect.
Power would be maintained
stable with increased monitoring
of plant parameters.
Operations
that upset plant stability will be stopped or not performed.
The AFD is required to be logged hourly not every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.B Incorrect.
Maintaining
power stable is correct, but frequecy of logging AFD is greater than that allowed by procedure.
C Incorrect.
Power reduction is incorrect as noted in A above.Plausible as frequency provided for logging AFD is correct.o Correct.Unit is maintained
in stable condition.
Increased monitoring
of AFD is required as the AFD alarm is inoperable
and frequency provided is correct.Monday, June 30, 2008 3:34:41 PM 147
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Emergency Procedures
/Plan: Knowledge of operator response to loss of all annunciators.
Question Number: Tier: Group: 3 4 Importance
Rating: 3.6 Technical Reference:
1-AP-6 (Whole procedure)
Proposed references
to be provided to applicants
during examination:
None Learning Objective:
U 11667 Question History: 10 CFR Part 55 Content: 41.10 Scramble Range:A-D NORTH ANNA o123456789 DCDBBCCBDD
Source If Bank: Difficulty
Level: Plant: Previous NRC?: NEW LOWER RO 6/2008 Source: Cognitive Level: Job Position: Date: Comments: KA Match: This item directly evaluates operator response to loss of control room annunciators
at 100%power.MCS Time: 1 Points: 1.00 Version:
Answer: Monday, June 30, 2008 3:34:41 PM 148
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY 75.G2.4.9 OOllBANKINORTH
ANNAlHIGHERlIROINORTH
ANNN6120081
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.*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 maximize CC flow to inservice RHR heat exchangers.
B:'" 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.
C.Stop RHR Pump1A and start RHR Pump 1 B and verify that RCS temperature
stabilizes.
D.Stop RHR Pump 1A and initiate the appropriate
attachment
for Alternate Core Cooling to control RCS temperature.
A Incorrect.
Actions appear correct and are very close to the required actions, except that level must be raised higher than 10 inches above Centerline.
B Correct.Actions provided minimize required net possitive suction head and increase available NPSH and are directed by the procedure to assess the condition of the RHR System prior to taking more radical actions.C Incorrect.
Plausible because stopping the pump would be performed subsequently
for the case where reducing flow was ineffective.
Since the pump would be air-bound, the other pump would not be started without venting.D Incorrect.
Plausible same as C, and also that alternate core cooling could be performed if that condition was reached.Again these actions are subsequent
to those that attempt to maintain the system in operation is the preferred method of decay heat removal.Monday, June 30, 2008 3:34:41 PM 149
QUESTIONS REPORT for NORTH ANNA NRC exam-RevO 04 15 08 RO ONLY Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: RCS temperature
indicators
Question Number: Tier: Group: Importance
Rating: Technical Reference:
1 1 3.6 1-AP-11 Proposed references
to be provided to applicants
during examination:
None Learning Objective:
None Question History: 10 CFR Part 55 Content: 41.10 Comments: KA Match: Item evaluates action required for a loss of RHA.One part of this is the indication
of RCS temperature
rising.While the item does not isolate'monitoring
of RCS temperature
indicators', the actions would be the same and the procedure does not differentiate
any actions based on temperature
alone.MCS Time: Source: Cognitive Level: Job Position: Date: Points: BANK HIGHER RO 6/2008 1.00 Version:0I23456789
Answer:BA ADD CDBDC Scramble Range:A-D Source If Bank: NORTH ANNA Difficulty
Level: Plant: NORTH ANNA Previous NRC?: Monday, June 30, 2008 3:34:41 PM 150