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Exam 05000338-08-301 - Draft RO Written Exam
	ML082381167
Person / Time
Site:	North Anna
Issue date:	08/21/2008
From:	; NRC/RGN-II
To:	;
References
	ER-08-301
	Download: ML082381167 (151)
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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:

RCS LP, Annunciator

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

PM 34

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

PM 35

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

PM 42

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

PM 50

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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

PM 51

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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

PM 69

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

PM 74

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

PM 77

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

PM 78

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

PM 80

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

PM 84

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

PM 85

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

PM 86

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

PM 91

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

PM 92

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

PM 93

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

PM 95

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

PM 96

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

PM 100

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

PM 101

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

PM 102

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 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 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

PM 108

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

PM 117

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

PM 120

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

PM 121

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

PM 124

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

PM 125

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

PM 126

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

PM 136

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .Plausible because RWST inoperability

for any reason other than temperature

or boron concentration

requires action within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to restore leakage to within limits.Plausible since an operator who is unfamiliar

with Tech Specs may feel that 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is appropriate

based on urgency of the situation.

Monday, June 30,20083:34:40

PM 139

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

PM 141

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

PM 145

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 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .B.Maintain reactor power stable;log AFD every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .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 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .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

@@ Line 14: / Line 14: @@
 | page count = 151
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-See also: [[followed by::IR 05000338/2008301]]
+See also: [[see also::IR 05000338/2008301]]
 =Text=

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