ML101130329

Written Examinations and Answer Keys (SRO)

ML101130329
Person / Time
Site:	Prairie Island
Issue date:	04/30/2010
From:	NRC/RGN-III
To:	Northern States Power Co, Xcel Energy
References
50-282/10-301, 50-306/10-301
Download: ML101130329 (177)

Text

f Name:----------------

EXAM 2010 PRAIRIE ISLAND IL T NRC WRITTEN Form: 0 Version: 0 1.001 AK3.01 002/001 AK3.0l/3.2/3.6/1/2/M/RO/N/N/FINAL Given the following conditions:

-Unit 1 is at 60%power and stable.-Control Bank D is at 174 steps.-The following THEN occurs:-Control Bank D rods start withdrawing.-A failure of automatic rod control is diagnosed.

-Rod Control is placed in Manual with Control Bank D at 177 steps.-All rod motion stops.-1 C5 AOP1, Uncontrolled Withdrawal of an RCCA, is entered.Control rods will be inserted in manual to the original height to...A.prevent exceeding AFD limits.B.prevent exceeding QPTR limits.C.restore RCS pressure to normal.restore Tavg to Tref.Justification:

A.Incorrect.

Plausible as AFD will be affected by the rod motion, but a 3 step change will not drive it out of band.B.Incorrect.

Plausible as rod motion will affect QPTR, but rods moving in a bank will NOT result in exceeding limits.C.Incorrect.

The Automatic pressure control system will increase spray flow to lower the RCS pressure rise caused by RCS temperature rise from the rod movement.Plausible if student thinks adjusting rods is necessary for RCS pressure control.D.Correct.Step 2.4.5 A.of 1C5 AOP1 directs the operator to adjust the rod position or RCS boron to restore Tave equal to Tref Wednesday, March 10,201010:23:37 AM 1 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the reasons for the following responses as they apply to the Continuous Rod Withdrawal:

Manually driving rods into position that existed before start of casualty Technical Reference(s):

1 C5 AOP1, Section 2.4 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8184L-005 Obj 5 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_.....:N...:.:/..:-A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43__Comments: Wednesday, March 10,201010:23:37 AM 2 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 2.001 K4.15 001/001 K4.15/2.7/3.01212/M/RO/N/N/FINAL Given the following conditions:

Unit 2 is at 30%power and stable.Control rod K7 is 15 steps lower than the other rods in control bank D.-The decision has been made to realign control rod K7 to control bank D per 2C5 AOP5, Misaligned Rod, Stuck Rod, and/or RPI Failure or Drift.To realign rod K-7, the crew will disconnect the lift coil(s)for...A.the affected GROUP (except K7)and adjust the affected GROUP step counter to the misaligned rod position.B:I the affected BANK (except K7)and determine the average RPI position for all rods.in the affected bank.C.control rod K7 and determine the average RPI position for all rods in the affected bank.D.control rod K7 and adjust-botttcontrol BANK D step counter;.ito the misaligned rod position.Justification:

A.Incorrect.

All lift coils in the affected bank (except K7)must be disconnected.

B.Correct.Refer to section 2.5.4 of 1 C5 A OP5 C.Incorrect.

All lift coils in the affected bank (except K7)must be disconnected.

The second part is correct.D.Incorrect.

All lift coils in the affected bank (except K7)must be disconnected.

Wednesday, March 10,201010:23:37 AM 3 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of eRDS design feature(s) and/or interlock(s) which provide for the following:

Operation of latching controls for groups and individual rods*Technical Reference(s):

1 C5 AOP5 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8184L-005 Obj 4b Question Source: Bank#_Modified Bank#_New---:.Xc...:...-

__Question History: Last NRC Exam_N/A._Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10,201010:23:38 AM 4 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 3.002 K5.19 002/002 K5.19/2.6/2.9/2/2JMJRO/N/N/FINAL Neutron embrittlement causes a(n)_----'in the reactor vessel nil ductility transition temperature and is used to determine?increase MINIMUM RCS temperature B.decrease MINIMUM RCS temperature C.increase MAXIMUM RCS pressure D.decrease MAXIMUM RCS pressure Justification:

A.Correct.PTLR indicates ART has been adjusted for radiation effects B.Incorrect.

Plausible as this is the affected RCS parameter, but not the correct affect on nil ductility temperature.

C.Incorrect.

Plausible as this is the appropriate change in nil ductility temperature, but pressure is not determined by nil ductility temperature at normal RCS temperature.

D.Incorrect.

Plausible due to symmetry and if neutron embrittlement is not understood by examinee.KIA Statement:

Knowledge of the operational implications of the following concepts as they apply to the ReS: Neutron embrittlement Technical Reference(s):

PTLR Section 4 (ART), GFES (PI-OPS-GFS-023L)

Proposed references to be provided to applicants during examination:

None Learning Objective:PI-OPS-GFS-023L Obj 6 Question Source: Bank#_Modified Bank#_New--,X,->-__QuestionHistory:Last NRC Exam_N/A_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43__Comments: Wednesday, March 10,201010:23:38 AM 5 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 4.003 K1.04 003/003 K1.04/2.6*/2.9*/2/1/M/RO/N/N/FINAL Given the following conditions:-1 ECA-O.O, Loss of ALL Safeguards AC power, is in effect.The seal water INJECTION is isolated to prevent_The seal water RETURN LINE is isolated to prevent_A.steam formation in the RCP Seals due to RCP thermal barrier heating.radioactive release within the Auxiliary Building due to overfilling the VCT.damage to RCP shaft when a charging pump is started as part of the recovery.radioactive release within the Auxiliary Building due to overfilling the VCT.C.radioactive release within the Auxiliary Building due to overfilling the VCT.steam formation in the RCP Seals due to RCP thermal barrier heating.D.steam formation in the RCP Seals due to RCP thermal barrier heating.damage to RCP shaft when a charging pump is started as part of the recovery.Justification:

A.Incorrect.

Plausible as this is the action for isolation of RCP thermal barrier CC system return in the same step of ECA-O.O and second part is correct.B.Correct.1 ECA-O.0 basis page 5 paragraph 1 states the seal return line is isolated to prevent overfilling the VCT and seal injection lines are isolated to prevent damage to the seal and shaft.C.Incorrect.

Plausible as both statements are basis from this step, but not applicable to the actions given.D.Incorrect.

Plausible as this is the action for isolation of RCP thermal barrier CC system return in the same step of ECA-O.0 and second partiscorrect.

Wednesday, March 10, 2010 10:23:38 AM 6 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems: CVCSTechnicalReference(s):

1 ECA-O.O Basis (page 5 of 14)Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-247 Obj 7 Question Source: Bank#_Modified Bank#_New

__Question History: Last NRC Exam_N/A'--_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43__Comments: Wednesday, March 10, 2010 10:23:38 AM 7 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 5.004 K5.07 002/004 K5.07/2.8/3.2/2/l/C/AIROININIFINAL Given the following conditions:

-Unit 1 is at 100%power and stable.-The Reactor Operator notices that N35&N36, Intermediate Range Nuclear Instrument startup rates are reading-0.1 DPM and stable.What is the cause of this event?A.Positive reactivity was added due to a mixed bed deminerializer with a higher boron concentration than the RCS was placed in service.B.Positive reactivity was added due to the boric acid makeup controller being set higher than RCS boron concentration.

C.Negative reactivity was added due to the Component Cooling water valve to the letdown heat exchanger failing open.Negative reactivity was added due to the RWST supply valve to the charging pump suction leaking by.Justification:

A.Incorrect.

Plausible as the statement is correct, but a positive reactivity would not result in a negative SUR.B.Incorrect.

Plausible as this would cause the stated reactivity change, but this reactivity change would not result in a negative SUR.e.Incorrect.

Plausible as this failure would cause a change in temperature which would cause a shift in boron concentration, but boron concentration would be reduce causing a positivereactivitychange and would result in a positive start up rate.D.Correct.System flow diagram XH-1-39 shows that a leaking RWST supply would introduce very high boron concentration water into the charging system.Wednesday.

March 10,201010:23:38 AM 8 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the operational implications of the following concepts as they apply to the eves: Relationship between SUR and reactivity Technical Reference(s):

XH-1-39 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8172L-001a

1. 7b Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_N/A_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43__Comments: Wednesday, March 10, 2010 10:23:38 AM 9 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 6.005 AAl.Ol 004/005 AAl.Ol/3.6/3A/l/2/C/A/RO/N/N/FINAL Given the following conditions:-1 C5 AOP5, Misaligned Rod, Stuck Rod, and/or RPI Failure or Drift, is in effect.-A Control Bank D rod was determined to be misaligned.

-Unit 1 is at 75%power.-Control Bank D is at 178 steps.-One Control Bank"D" rod indicates at 150 steps.-The appropriate lift coil disconnects were placed in disconnect.

-The in-hold-out lever was taken to"IN" to determine if the rod is stuck or misaligned.

Which of the following indicates a STUCK rod?TAVE RPIconstant constant B.constant decrease C.decrease decrease D.decrease constant Justification:

A.Correct.Step 2.4.2.C.6.e of 1C5 AOP5 indicates the cause for this is a Stuck Rod B.Incorrect.

Plausible as if step counter operation is confused with RPI operation.

C.Incorrect.

Plausible if indications are selected for a misaligned rod.D.Incorrect.

Plausible if RPI failured is assumed and/or disconnect switches are assumed to effect RPl's.Wednesday, March 10, 2010 10:23:38 AM 10 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to operate and/or monitor the following as they apply to the Inoperable

/Stuck Control Rod: CRDS Technical Reference(s):

1C5 AOP5 step 2.4.2.C.6.e Proposed references to be provided to applicants during examination:

None Learning Objective:

P8184L-005 Obj.3 Question Source: Bank#_Modified Bank#_New-,X-,-__Question History: Last NRC Exam_-=-N..:.:/..:....A:.....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10, 2010 10:23:38 AM 11 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 7.005 K3.01 002/005 K3.01/3.9/4.0/2/1/C/A/RO/N/N/FINAL Given the following conditions:

-Unit 1 is in MODE 4-12 RHR pump is in service for cooldown.-12 RCP is running.-RCS temperature is being maintained constant at 330°F.-CV-31236, 12 RHR HX RC OUTLET FLOW, air supply line breaks.As a result of the loss of air, the control valve will fail and RCS temperature will__.A'Iopen, lower to a new value B.open, lower then return to original value C.closed, rise then return to original value D.closed, rise to a new value Justification:

A.Correct, XH-1-39 indicates CV-31236 is a fail open valve and would increase cooling to the RCS.B.Incorrect.

Plausible since CV fails open and if it is incorrectly assumed the bypass valve will compensate for this failure.C.Incorrect.

Plausible if CV failure mode is not known and it is assumed the bypass valve will compensate for the failure.D.Incorrect.

Plausible if student thinks CV fails closed as this is the proper temperature response for CV failing closed.Wednesday, March 10,201010:23:38 AM 12 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the effect that a loss or malfunction of the RHRS will have on the following:

ReS Technical Reference(s):

XH-1-31, B15, RHR System Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-003

1. 3d Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:38 AM X 13 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 8.006 K6.02 003/006 K6.02/3.4/3.9/2/l/C/NRO/N/N/FINAL Given the following conditions:-A cooldown to COLD SHUTDOWN is in progress.-RCS Tavg is 400°F.-RCS pressure is 990 psig.-BOTH SI Accumulator Discharge Isolation supply breakers are ON.-MV-32071, 11 Accumulator Isolation valve is closed with its switch in AUTO.-MV-32072, 12 Accumulator Isolation valve is open with its switch in AUTO.-LOOP B suffers a DESIGN BASIS LOCA.-Containment pressure peaks at 10 psig.11 Accumulator will_12 Accumulator will---------A.be isolated by MV-32071 inject into the Reactor Vessel B.be isolated by MV-32071 spill onto the containment floor C.inject into the Reactor Vessel inject into the Reactor Vesselinject into the Reactor Vessel spill onto the containment floor Justification:

A.Incorrect.

Plausible as Safety injection is bypassed, but the containment pressure initiation at 3.5 psig is not bypassed.11 accumulator discharge valve will auto open on the SI signal and inject into the RCS and if assumptions of design basis LOCA are not known.B.Incorrect, Plausible as this is the correct response of the 12 accumulator, and Safety injection is bypassed, but the containment pressure initiation is not bypassed.12 accumulator will dump into containment due to the break location.C.Incorrect.

Plausible as this is the correct response of the 11 accumulator, and if assumptions of design basis LOCA are not known.D.Correct.SI actuates on 3.5 psig containment pressure which opens the discharge valve on 11 Accumulator and 12 Accumulator goes to the floor of containment through the break.Wednesday, March 10,201010:23:38 AM 14 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Core flood tanks (accumulators)

Technical Reference(s):

TS 3.5.1, 1 C1.3 step 5.5.16, USAR section 6.2.2.2.1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P9180L-005 Obj 9b Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_-:N..;.;/.;...A.:..--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10,201010:23:38 AM 15 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 9.007 EK2.02 001/007 EK2.02/2.612.8/1/1/C/A/RO/N/B/FINAL Given the following conditions:

-Unit 1 is at 16%power and stable.-Frequency on Bus 11 and 12 goes to 57 HZ for one (1)second AND returns to 60 HZ.What are the positions for the RCP breakers and the Reactor Trip breakers?Rep Breakers Reactor Trip Breakers A'!Open Open B.Open Shut C.Shut Shut D.Shut Open Justification:

A.Correct.58.275 trips RCP breakers.both RCP breakers open gives Rx trip B.Incorrect, see A.C.Incorrect, see A D.Incorrect, see A KIA Statement:

Knowledge of the interrelations between a reactor trip and the following:

Breakers, relays and disconnects Technical Reference(s):

B8, 47005-0301, 0302 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8184L-004 Obj 3e Question Source: Bank#P8184L-004 028 Modified Bank#_New_Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10,201010:23:38 AM 16

'.2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 10.007 K3.01 001/007 K3.0l/3.3/3.6/2/l/C/AIROIN/B/FINAL Given the following conditions:

-Unit 1 is at 100%power.-A Reactor trip AND Safety Injection occur.-Several minutes after the Safety Injection, the following indications are noted:-Containment Radiation Monitors are in HIGH alarm.-Containment humidity is rising.-Containment pressure is rising.-47016-0304, CONTAINMENT SUMP A LEVEL HIGH, is LIT.-47012-0406, PRZR RELIEF TANK HI TEMP/LVLlPRESS OR LO LVL, is LIT.What has caused the above indications?

A'!A Pressurizer PORV is stuck open.B.A RCP#1 seal has failed.C.A Steam Generator Blowdown piping connection has severed.D.An Incore Thimble Tube has ruptured atthebottom of the reactor vessel.Justification:

A Correct.A stuck open Pressurizer PORV will fill up the PRT and blow the rupture disc leading to high containment humidity, pressure, and radiation levels.B.Incorrect.

Plausible if the student believes the#1 seal failure will cause a leak to containment, or that the#1 sealleakoff could go the PRT instead of the VCT.C.Incorrect.

Plausible because this will increase pressure and humidity in containment, but will not increase radiation levels and will not fill up the PRT.D.Incorrect.

Plausible as this failure will fill up the thimble tube and leak to the seal table.This will increase radiation levels, humidity, and pressure in containment but will not fill up the PRT.Wednesday, March 10,201010:23:39 AM 17 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Know/edge of the effect that a loss or malfunction of the PRTS will have on the following:

Containment Technical Reference(s):

1C4 AOP1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8170L-003 Obj 3d, 4b Question Source: Bank#P8170L-003-100 Modified Bank#_New_Question History: Last NRC Exam_--'N....:.:/..:...A.:-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10,201010:23:39 AM x 18 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 11.008 A2.08 001/008 A2.08/2.5/2.7*/2/1/C/AIRO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power-CV-31202, 11 Letdown Heat Exchanger Temperature Control Valve, CLOSES due to a malfunction.

As a result, Letdown temperature will and the operator will be required to A.decrease, verify Letdown diverts to the VCT B!"'" increase, verify Letdown diverts to the VCT C.increase, borate per 1C12.5, Boron Concentration Control D.decrease, dilute per 1C12.5, Boron Concentration Control Justification:

A.Incorrect.

Plausible as this is the appropriate reaction to the casualty, but wrong trend on letdown temperature.

B.Correct.C.Incorrect.

Plausible as this is the correct temperature trend, but the wrong mitigation action.D.Incorrect.

Plausible as this is the correct response if it's assumed the temperature change has a significant effect on RCS temperature.

Wednesday, March 10, 2010 10:23:39 AM 19 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to (a)predict the impacts of the following malfunctions or operations on the CCWS, and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Effects of shutting (automatically or otherwise) the isolation valves of the letdown cooler.Technical Reference(s):

B14 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8172L-001A Obj 3e, 4b.Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_....:N-"/..:...A-'--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41----:5::...-_

55.43_Comments: Wednesday, March 10,201010:23:39 AM 20 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 12.008 AAl.Ol 00l/008 AAl.Ol/4.2/4.0/l/l/C/A/ROININ/FINAL Given the following conditions:

-Unit 1 is at 50%power.-One of the Pressurizer PORVs is leaking by.-C47012-0109, Przr Safety I Relief Valve Flow, is LIT.The crew is required to close__BlockValve(s) and monitor for lowering_A'!ONE, Pressurizer Relief Valve outlet temperature B.BOTH, Pressurizer Relief Valve outlet temperature C.ONE, Pressurizer Relief Tank liquid temperature D.BOTH, Pressurizer Relief Tank liquid temperature Justification:

A.Correct.1C4 AOP1, Table 1.B.Incorrect.

Plausible as this will isolate the leaking PORV, but it is not procedurally directed.C.Incorrect.

Plausible as sequential isolation is procedurally directed, but PRT liquid temperature is not used in this procedure.

D.Incorrect.

Plausible as this will isolate the leaking PORV and PRT temp will change, but these actions are not procedurally driven.Wednesday, March 10,201010:23:39 AM 21 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to operate and/or monitor the following as they apply to the Pressurizer Vapor Space Accident: PZR spray block valve and PORV block valve Technical Reference(s):

1 C4 AOP1, Table 1, C47012-01 09 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-235 Obj A5 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_--:N....:,:/:.,:..A.:-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10, 2010 10:23:39 AM 22 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 13.010 2.4.11 004/010 2.4.11/4.0/4.2/2/1/M/ROININ/FINAL Given the following conditions:

-Unit 1 is at 100%power.-The Blue Channel Pressurizer Pressure fails LOW.-C47012-0608, PRZR Control HI Press or Backup HTRS ON, is LIT.Upon completion of operator actions, bistables will have been tripped for the instrument in order to ensure-----------

A.overpressure protection coincidence is available B.control and alarm functions are no longer affected by the failed channelappropriate protective signals are generated with the blue channel out of service D.subsequent testing of the blue channel does not cause additional transients to the plant Justification:

A.Incorrect.

Plausible since the instrument failing low does result in a loss of overpressure protection, however the bistables associated with the overpressure protection are controlled by changing the controlling pressurizer pressure channel and are not tripped by operator action.B.Incorrect.

Plausible as these actions will be achieved by operator action follOWing the failure, but this is not the function of tripping the bistables.

C.Correct.All bistables are tripped to ensure coincidence can be met for reactor protection functions.

D.Incorrect.

Plausible as the bistables will be cycled by the maintenance, but at this time the channel will not be controlling and therefore would not cause plant transient.

Wednesday, March 10, 2010 10:23:39 AM 23 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Pressurizer Pressure Control: Knowledge of abnormal condition procedures.

Technical Reference(s):

1 C51.3 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-251 ATT3 Obj 3 Question Source: Bank#_Modified Bank#_New----'X-'-__Question History: LastNRCExam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:39 AM x 24 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 14.010 K4.03 001/010 K4.03/3.8/4.1/2/1/C/A/ROIN/B/FINAL Given thefollowingconditions:

-Cooldown is in progress per1C 1.3, Unit 1 Shutdown.-RCS temperature 320°F and stable.-RCS pressure 340 psig and stable.-11 RHR pump is in service.-OPPS has just been enabled.-1PT-419, RCS Hot Leg Pressure Transmitter, spikes HIGH.What is the plant response?MV-32231, Loop 8 Hot Leg to RHR Pump SUCTION, will CLOSE.80th PRZR PORV's will OPEN.B.MV-32066 Loop 8 Cold Leg RHR INJECTION, will CLOSE.80th PRZR PORV's will stay CLOSED.C.MV-32231 Loop 8 Hot Leg to RHR Pump SUCTION will CLOSE.80th PRZR PORV's will stay CLOSED.D.MV-32066 Loop 8 Cold Leg RHR INJECTION, will CLOSE.80th PRZR PORV's will OPEN.Justification:

A.Correct.B.Incorrect.

Plausible as most systems isolate discharge rather than supply to allow for recirc, but not in this system.PORVoperation is plausible if assumed 2/4 logic as in a normal setup.C.Incorrect.

Plausible as this is the correct valve to isolate and if PORV logic is assumed to require 2/4 logic as normal.D.Incorrect.

Plausible as most systems isolate discharge rather than supply to allow for recirc, but not in this system and PORV response is correct.Wednesday, March 10, 2010 10:23:39 AM 25 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of PZR pes design feature(s) and/or interlock(s) which provide for the following:

Over pressure control Technical Reference(s):

B15, P8184L-003 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-003 Obj 7 Question Source: Bank#P8180L-003-9 Modified Bank#_New_Question History: Last NRC Exam_-:N...:,:/.:..A"--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:39 AM 26 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 15.011 EA2.11 002/011 EA2.11/3.9/4.3/1/1/MIRO/N/N/FINAL A Unit 1, Large Break LOCA is in progress.The FIRST SI pump is required to be secured once...A.RCS pressure is<550 psig.B.RHR flow is verified>950 gpm AND RCS pressure is<550 psig.C.RWST level reaches 33%AND ONE train of Safeguards Pumps verified available for recirculation.RWST level is below 33%AND BOTH trains of Safeguards Pumps verified available for recirculation.

Justification:

A.Incorrect.

Plausible as this is the pressure used in adverse containment to determine if SI pumps are required to be restarted.

B.Incorrect.

Plausible as this is pressure and flow conditions used to verify that SI pumps are no longer required.C.Incorrect.

Plausible as this is the level at which you transition to 1 ES-1.2, Transfer to Recirculation where SI pumps will be secured, but both trains must be verified available.

D.Correct.At 33%the info page directs entry into 1ES-1.2 then SI pumps are stopped once both trains are verified operating.

KIA Statement:

Ability to determine or interpret the following as they apply to a Large Break LOCA: Conditions for throttling or stopping HPI Technical Reference(s):

1 ES-1.2 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT 34 Obj 5a Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_-:N....:,:/..:...A:..--

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:39 AM 27 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 16.012 K1.05 001/012 K1.05/3.8*/3.9/2/1/C/AIRO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power.-SP 1035B, Reactor Protection Logic Test at Power-Train B, is in progress.-Reactor Trip Breaker"A" is CLOSED.-Reactor Trip Bypass Breaker"A" is racked to DISCONNECT.

-Reactor Trip Breaker"B" is OPEN.-Reactor Trip Bypass Breaker"B" is CLOSED.What is the system response following an inadvertant Safety Injection signal AND Reactor Trip Bypass Breaker"B" fails to OPEN?A.Rods fail to insert.B.Turbine fails to trip.Train"B" Safety Injection signal can NOT be RESET.D.Steam dumps fail to arm.Justification:

A.Incorrect.

Reactor trips due to Reactor Trip Breaker':4" opens.B.Incorrect.

Plausible if candidate thinks reactor trip to turbine trip logic is train specific C.Correct.'B'train P-4 contacts won't allow Train'B'SI to reset D.Incorrect.

Reactor Trip Breaker':4" opening trips the turbine which arms to steam dump.KIA Statement:

Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems: ESFAS Technical Reference(s):

B18C, Figure B18C-6 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-004 Obj 3 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41-L.JL 55.43__Comments: Wednesday, March 10,201010:23:39 AM 28 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 17.013 K2.01 001/013 K2.01/3.6*/3.8/2/1/C/A/RO/N/N/FINAL Given the following conditions:-1 E-1, Loss of Reactor or Secondary Coolant, is in progress.-Safety Injection signal is RESET.Offsite Power is THEN lost.-01 and 02 start and load onto Bus 15 and Bus 16.-The Safety Injection pumps are no longer running, BUT they were verified running before the Loss of offsite power.Should the SI pumps have restarted automatically upon restoration of power and why?A'!Yes, the pumps should have started because the breakers remained closed.B.Yes, the SI signal should have re-initiated once power is restored.C.No, the sequencer will start the SI pumps in 5 seconds.D.No, the SI signal has been reset.Justification:

A.Correct.B.Incorrect.

Power restoration has no input into the SI signal.C.Incorrect.

The SI pumps are not part of the sequencer, 5 seconds is for RHR pumps.D.Incorrect.

The SI pump breakers will remain closed during the loss of power to the safeguards buses.The SI pumps are not part of the sequencer and, therefore, their breakers do not open upon loss of power.As a result when power is restored the SI pumps will resume operation regardless of whether an SI signal is present.With the SI signal reset, no further automatic SI signal will be generated to restart safeguards equipment.

Normal sequencing of safeguards loads onto the emergency bus after diesel generator startup will not occur and will have to be done manually.Wednesday, March 10, 2010 10:23:39 AM 29 2010 PRAIRIE ISLAND ILT NRC WRITTEN EXAM KIA Statement:

Knowledge of bus power supplies to the following:

ESFAS/safeguards equipment control Technical Reference(s):

B18C, B20.5-3 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-004 Obj 3e Question Source: Bank#_Modified Bank#_New--,Xc..:...-

__Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday.

March 10,201010:23:39 AM 30 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 18.015 K1.03 003/015 K1.03/3.1*/3.1/2/2/C/A/RO/N/B/FINAL Given the following conditions:

-Unit 1 is at 80%power and stable.-A control rod is suspected of partially inserting into the core.-Currently the control rod indicates approximately 40 steps by Individual Rod Position Indication (IRPI).-This control rod is located adjacent to Power Range instrument N-44.What selection supports the diagnosis of an actual mispositioned rod and why?A.ALL Power Range Nuclear instruments will read slightly LOWER than pre-event values due to HIGHER moderator density.8.ALL Power Range Nuclear instruments will read slightly LOWER than pre-event values due to NEGATIVE reactivity insertion.Annunciator 47013-0201, Power Range Negative Flux Rate Channel Alert, is LIT due to HIGH localized power reduction.

D.N-44 delta I indicates MORE POSITIVE due to flux shift to a HIGHER enriched region of the core.Justification:

A.Incorrect.

This distractor used based on RCS temperature perturbations affecting NI indications.

Lower temperature causes more thermalization in the core and less leakage to the NI.This is why NI indication actually decreases, any error in this reasoning would lead to this distractor being selected.B.Incorrect.

Plausible if it is incorrectly assumed overall power will decrease due to the inserted rod.C.Correct.D.Incorrect.

Local flux would be driven to the bottom, however since power is distributed, it is plausible that overall flux will shift to the top.This actually occurs with banks of rods at EOL, due to lack of enriched fuel at the bottom of the core.Wednesday, March 10,201010:23:40 AM 31 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the physical connections and/or cause-effect relationships between the HIS and the following systems: eRDS Technical Reference(s):

C47013-0201, 1 C5 AOP5 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-230 OBJ A5 Question Source: Bank#P8184L-002-57 Modified Bank#_New---Question History: Last NRC Exam_--'N...:.:/..:...A.:.-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43__Comments: Wednesday, March 10, 2010 10:23:40 AM 32 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 19.0222.4.46002/022 2.4.46/4.2/4.2/1/1/C/A/RO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power.-12 Charging pump is out of service.-C47015-0208

&0209, 11&12 RCP#1 Seal Inlet or Outlet Hi Temp are LIT.-All RCP seal water return temperatures have slowly risen from 150°F to 195°F.-C47015-0206

&0207, 11&12 RCP Labyrinth Seal La DIP, are LIT.What would cause these conditions?

A.Loss of Reactor Makeup due to 4.16KV Safeguards Bus 15 locks out.Loss of Reactor Makeup due to 4.16KV Safeguards Bus 16 locks out.C.Loss of Seal Injection due to Seal water return line blockage.D.Loss of Seal Cooling due to 12 RCP#2 Seal failing.Justification:

A.Incorrect.

Plausible if the charging pumps are assumed to be powered odd pump to odd supply like most systems.B.Correct.With the loss of Bus 16 Charging pumps 11 and 13 will not have a power supply.Therefore all reactor makeup capability will be lost causing the given alarms.C.Incorrect.

Plausible as this will cause the temperature transients indicated, but not the changes in dip.D.Incorrect.

Plausible as this will cause the temperature transients indicated, but not the changes in dip.Wednesday, March 10,201010:23:40 AM 33 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

022 Loss of Reactor Coolant Makeup 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

Technical Reference(s):

B12A, 1C12.1 AOP1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT 25 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_--'N...:.:/..:...A'-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43_Comments: Wednesday, March 10,201010:23:40 AM 34 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 20.022 Kl.04 002/022 Kl.04/2.9*/2.9*/2/1/C/AIRO/N/BIFINAL Given the following conditions:

-BOTH units are at 100%power-Chilled Water is aligned to ALL CFCUs and CRDM cooling units.-Unit 2 experiences a Safety Injection.

What is the expected cooling lineup for Unit 1 and Unit 2?Unit 1 FCU's Unit 1 CRDM's Unit 2 FCU's Unit 2 CRDM's A.Cooling Water Isolated Chilled Water Chilled Water B.Chilled Water Chilled Water Cooling Water Isolated C.Chilled Water Chilled Water Chilled Water Chilled WaterCooling Water Isolated Cooling Water Isolated Justification:

A.Incorrect.

Plausible if confuse SI effect on both units.B.Incorrect.

Plausible if confuse SI effect on both units.C.Incorrect.

Plausible if confuse SI effect on both units.D.Correct.KIA Statement:

Knowledge of the physical connections and/or cause effect relationships between the CCS and the following systems: Chilled Water Technical Reference(s):B19,B35, B37A, NF-86186-3, 2E-O An.L Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-009H Obj 4 Question Source: Bank#P8180L-009H 043 Modified Bank#_New_Question History: Last NRC Exam_-=2:.;:0:..::0-:.4-,R:...,:.O=-:.N..:.:R...:..C=....:::E::.,.XA",-,,-,M:..:..-_

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 1°CFR Part 55 Content: 55.41_9_55.43__Comments: Wednesday, March 10, 2010 10:23:40 AM 35 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 21.025 AKl.Ol 001/025 2.1.2/3.0/4.0/1/1/C/A/ROIN/BIFINAL Given the following conditions:

Unit 1 is in Reduced Inventory with Train'A'RHR providing shutdown cooling.The following indicationsarethen noted:-RCS ultrasonic level is 12 inches and decreasing rapidly.-11 RHR flow was initially 1000 gpm and is now reading near ZERO and is fluctuating.

-11 RHR pump amps are low and fluctuating.

What action is required to be taken FIRST to mitigate these conditions?

A.Start 12 RHR pump.Stop 11 RHR pump.C.Remove letdown from service.D.Direct the containment rover to vent RHR piping.Justification:

A.Incorrect.

Plausible as this would preserve cooling, however with a common header it would result in air binding of 12 RHR pumps.B.Correct.Per step 2.4.3 of D2 AOP1"Loss of Coolant in a Reduced Inventory Condition." Stopping the pump will stop the air ingestion and prevent damage to the RHR pump, preserving it for restart once the loss of level is stopped and level is recovered.

Also, RHR is a likely source of inventory loss C.Incorrect.

Plausible as this may slow level loss if the failure is in the CVCS system, but it would not prevent damage to RHR pump from air ingestion.

D.Incorrect.

Plausible as this is an appropriate action if the pump were merely cavitating, however the pump does not have a water supply.Questions tests impact of low RCS level on RHR system (air ingestion) and appropriate recovery sequence.12 inch RCS level is below midloop and results in vortexing at the RHR inlet Wednesday, March 10, 2010 10:23:40 AM 36 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Loss of RHR, Knowledge of operator responsibilities during all modes of plant operation.

Technical Reference(s):

D2 AOP1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT 38 Question Source: Bank#P8140L-107 2 Modified Bank#_New_Question History: Last NRC Exam_-=2::.;::0:.=;0....:.4--,R:...,:.O=-:.N..:.,oR...:..C=..=E::..XA:::....:.:.:M:.:-_

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10, 2010 10:23:40 AM 37 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 22.026 A1.05 001/026 A1.05/3.1/3.4/2/1/C/AIROfN/B/FINAL Given the following conditions:

-A large break LOCA occurred on Unit 1.-Containment spray has actuated.-Containment pressure is lowering.-RWST level is 40%and slowly lowering.-Caustic Addition Standpipe level is 96%and stable.What is the plant effect of these conditions?

A.Containment pressure peaks at a higher value due to reduced heat capacity of the spray.Corrosion of components in containment increases due to the lower pH of the spray.C.Containment radiation levels are higher due to increased iodine gas production.

D.Containment hydrogen peaks at a higher value due to reduced scrubbing from the spray.Justification:

A.Incorrect.

Plausible if effect of pH on heat capacity is unknown.B.Correct.CA standpipe is at normal operating level, indicating that there has been no injection of caustic in spray flow.This will result in less neutralizing (lower pH)of containment sump.C.Incorrect.

Plausible if effect of spray on iodine not recognized and fact that iodine will not increase rad levels.0.Incorrect.

Plausible if effect of NaOH in the spray water on hydrogen not known.Wednesday, March 10,201010:23:40 AM 38 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)associated with operating the CSS controls including:

Chemical additive tank level and concentration Technical Reference(s):

B18D, C47019:0103 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-003 Obj.3 Question Source: Bank#P8180L-002019 Modified Bank#_New---Question History: Last NRC Exam_--'N....::/"-A.:...-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41_5_55.43__Comments: Wednesday, March 10,201010:23:40 AM 39 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 23.026 A4.05 002/026 A4.05/3.5/3.5/2/l/M/RO/N/NIFINAL Given the following conditions:-A large break LOCA occured on Unit 1.-Containment pressure peaked at 30 psig and has lowered to 10 psig.-Per 1 ES-1.2, Transfer to Recirculation, the Containment Spray signal is being RESET.-CS-46001, Containment Spray Reset Train A, has been depressed.

-C47019-01 03, Containment Spray Actuated, is LIT.C47019-0103, Containment Spray Actuated annunciator window be LIT because---------should, both trains must be reset to clear this alarm B.should, the Containment Spray pumps must be stopped C.should NOT, only ONE train needs to be reset to clear this alarm D.should NOT, containment pressure is below the 23 psig setpoint Justification:

A.Correct.B.Incorrect.

Plausible as pumps operating is a common alarm criteria, but not in this case and the alarm should be lit.C.Incorrect.

Plausible as either train will cause the alarm to light, but both must be reset to clear it.D.Incorrect.

Plausible as many systems actuation signals will clear when the conditions are no longer met, but not this system.Wednesday, March 10,201010:23:40 AM 40 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to manually operate and/or monitor in the control room: Containment spray reset switches Technical Reference(s):

47019-0103, B18D Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-002 Obj 3.Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_N/A._Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10, 2010 10:23:40 AM X 41 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 24.026 AA1.07 001/026 AA1.07/2.9/3.0/l/1/MIRO/N/N/FINAL Given the following conditions:-A Loss of All AC power has occurred on Unit 1.-After 10 minutes, power was restored to Bus 15.-1 ECA-0.1, Loss of All Safeguards AC Power Recovery Without SI Required, is in progress.-Actions to start a component cooling pump are being performed.

Why are CC-16-2 and CC-16-3, RCP CC Return Manual Isolation Valves verified closed prior to restarting the component cooling pump?A':I Prevent steam introduction into the component cooling pumps.B.Reduce component cooling heat loads to the minimum based on cooling water loads.C.Prevent damage to the RCP Motor bearings due to excessive cooldown rate.D.Maximize flow to the CVCS components for re-establishing charging, letdown, and seal return.Justification:

A.B.c.D.Correct.See Below Incorrect.

Plausible as reducing heat loads is a required action for this procedure, however is not the basis for these valves being closed.Incorrect.

Plausible as thrust bearing cooling is important, but is not a concern for the motor bearings.Incorrect.

Restoring CVCS loads is done in subsequent steps, but is not the basis for this step.The purpose of this step is to prevent potential RCP seal damage and the introduction of steam into the component cooling water system when a CC pump is started.The operator should check the status of RCP seal isolation in preparation for loading the charging pumps and CC pump on the safeguards bus.If the RCP has been isolated (by local actions specified in 1 ECA-O.O), the operator proceeds to Step 2.If the operator determines that the sealinjectionisolation valves are open or their position is not known, the operator should check charging pump status.If a pump is running, the operator is instructed to go to Step 2 to continue plant recovery.If a charging pump is not running, the operator should attempt to isolate the seal injection line by dispatching personnel to locally close the seal injection isolation valves.The operator should not start a charging pump until sealinjectionis isolated to avoid potential RCP damage.If the operator determines that the thermal barrier CCreturnisolation valves are open, the operator should check CC pump status.If a pump is running, the operator is instructed to go to Step 2 to continue plant recovery.In this situation, the CC pump has already started upon AC power restoration and thermal barrier flow has been initiated.

The operator should be aware of potential CC operational problems.If the CC pumps are not running, the operator is instructed to close the CC return isolation valves.Wednesday, March 10,201010:23:40 AM 42 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water: Flow rates to the components and systems that are serviced by the CCWS;interactions among the componentsTechnicalReference(s):

1 ECA-O.O Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT.47 Obj 5 Question Source: Bank#

Modified Bank#_New X Question History: Last NRC Exam_N/A,_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10, 2010 10:23:40 AM 43 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 25.027 AK2.03 001/027 AK2.03/2.6/2.8/1/1/C/A/ROIY/BIFINAL The controlling pressurizer pressure channel fails to 2230 psig.What is the expected behavior of the pressurizer pressure control board master controller deviation and output meters?Deviation Meter A'f'Slightly negative B.Pegged low C.Slightly positive D.Pegged high Justification:

Output Meter Steadily decreasing to 0 32.5%and stable 67.5%and stable Steadily decreasing to 0 A.Correct.Actual minus setpoint=-5 psig, with deviation of 1 psig/%so-4.375%.Since"actual" (as measured by controlling channel)pressure never changes, integral will cause output to decrease to a over the next minute.B.Incorrect.

Deviation is incorrect, output assumes no integral.C.Incorrect.

Deviation in wrong direction, incorrect output.D.Incorrect.

Assumes system controlling to this pressure.KIA Statement:

Knowledge of the interrelations between Pressurizer Pressure Control Malfunctions and the following:

Controllers and positioners Technical Reference(s):

C7 , B7 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8170L-005, Objective 3 Question Source: Bank#P8170L-005 52 Modified Bank#_New_Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:41 AM 44 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 26.027 K2.01 001/027 K2.01/3.1*/3.4*/2/2/C/AIRO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power.-01 Diesel Generator is out of service.-4.16KV Safeguards Bus 16 LOCKS OUT.__FCU's are operating and Containment Cooling System T.S.LCO requirements are_A.NO NOT met B.NO met Col TWO NOT met D.TWO met Justification:

A.Incorrect.

Plausible if candidate fails to realize Bus 15 will be powered from an offsite source.B.Incorrect.

Plausible if candidate fails to realize Bus 15 will be powered from an offsite source, but believes the Bus 15 fansarestill operable T.S.requirements are met.C.Correct.2 fans are running and both trains are required by T.S.D.Incorrect.

Plausible as two fans are running and are sufficient for design basis cooling needs, but does not meet T.S.requirements.

Fan coil units#11[21 J and#13[23J are powered from safeguards MCC 1 X Bus 1[MCC 2X Bus 1].Fan coil units#12[22J and#14[24J are powered from safeguards MCC 1 X Bus 2[MCC 2X Bus 2].Fan coils#-1 and#-3 receive signals from Train A of the engineered safety features (ESF)and fan coils#-2 and#-4 receive signals from Train B of ESF.Fan running lights on the control board indicate the fan running speed.Control of the cooling water valves associated with the fan coil units is discussed in B-35.Wednesday, March 10, 2010 10:23:41 AM 45 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of bus power supplies to the following:

fans Technical Reference(s):

B19, Load List, T.S.3.6.5 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-009H Obj 7 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_.....:N'-'-'/"-A-=----

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10,201010:23:41 AM 46 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 27.0282.4.31001/028 2.4.31/4.2/4.1/1/2/C/AIROIN/BIFINAL Given the following conditions:

-Unit 1 is at 100%power.-Pressurizer level selector switch is in the (2/3)White/Blue position.The variable leg of the blue channel of pressurizer level develops a leak.Which of the following is the response of the pressurizer level control system to this leak?A.ONLY the high level alarm will annunciate.

B.ONLY the low level alarm will annunciate and letdown will isolate.C.The level deviation alarm will annunciate, B/U heaters will energize, and charging pump speed will lower to minimum.The level deviation and low level alarms will annunciate, letdown will isolate, and charging pump speed will increase to maximum.Justification:

A.B.C.D.Incorrect.

This alarm comes from the (white)bistable channel not the controlling channel.Incorrect.

Incomplete response, only 2 of the plant responses used.Incorrect.

Opposite charging response, plausible if variable leg leak is diagnosed to fail the controlling channel high.Correct.Variable leg leak will cause the controlling channel to fail low.Wednesday, March 10, 2010 10:23:41 AM 47 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Pressurizer Level Malfunction, Knowledge of annunciator alarms, indications, or response procedures.

Technical Reference(s):

1 C51.3, Figure B7-20 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8179L-006 Obj 3 Question Source: Bank#P8170L-006-9 Modified Bank#_New_Question History: Last NRC Exam_....;N....::/"-A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:41 AM x 48 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 28.029 EA2.02 001/029 EA2.02/4.2/4.4/1/1/C/AIROININIFINAL Given the following conditions:

-Unit 1 is at 100%power.-C47017-0304, 11 STM GEN LO-LO LVL Reactor Trip, first out annunciator is LIT.The required crew response is to_A.initiate a manual Safety Injection and enter 1 E-O B.manually insert control rods if power is greater than 5%C.manually open the FRV to feed 11 S/G back into normal bandverifyVS/G levels are below the reactor trip setpoints, THEN manually trip the reactori(Justification:

A.Incorrect.

Plausible if student assumes 10-10 level is indicative of an event which would require S/.B.Incorrect.

Plausible as this is an immediate action for FR-S.1, but not required before E-O actions.C.Incorrect.

Plausible as this would remedy the 10-10 S/G level, but is not the appropriate response.D.Correct.Either the RO or the BOP are authorized to initiate a reactor trip prior to or while concurrently informing the SRO.KIA Statement:

Ability to determine or interpret the following as they apply to a A TWS:Reactortrip alarm Technical Reference(s):

FP-OP-COO-01, 1 E-O, Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-224 Obj 2 Question Source: Bank#_Modified Bank#_New X---'----

Question History: Last NRC Exam_--'N...:,:/-"-A.:-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.4155.43 Comments: Wednesday, March 10,201010:23:41 AM 49 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 29.029 K3.01 002/029 K3.01l2.9/3.1I2/2/C/A/RO/N/N/FINAL Given the following conditions:

-Unit 1 in Mode 5.-Containment Air Lock Doors are CLOSED.-Containment In-Service Purge system is in service.-C47048 1 R-11, Cntmt/Shield Bldg Vent Air Particle Monitor, alarms HIGH.-In-Service purge Exhaust Dampers do NOT CLOSE when required.As a result, containment pressure will due to_A.remain constant exhaust dampers closing on interlock with the supply dampers B.remain constant both supply and exhaust fans trippingdecrease the continued exhaust fan operation D.increase the continued supply fan operation Justification:

A.Incorrect.

Plausible as some systems have supply/exhaust interlocks, but this system is not one of them.B.Incorrect.

Plausible as often the pumpslfans will be tripped rather than dampers closed, but not in this system.C.Correct.D.Incorrect.

Plausible as the supply fan does remain operating, but it is isolated by the associated dampers.Wednesday, March 10,201010:23:41 AM 50 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the effect that a loss or malfunction of the Containment Purge System will have on the following:

Containment parameters Technical Reference(s):

B19, 1C19.2, NF-40762-2 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-009E Obj 3e Question Source: Bank#_Modified Bank#_New--'X'-'--__Question History: LastNRCExam_....:N....:.;/..:-A.:...-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10, 2010 10:23:41 AM 51 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 30.035 K6.02 001/035 K6.02/3.1/3.5/2/2/C/A/RO/N/NIFINAL Given the following conditions:

-Unit 1 is at 100%power.Subsequently the following conditions are observed:-11 SG Pressure is 680 psig and lowering.-11 SG Level is 52%NR and rising.-11 SG Steam Flow is 3.6 x 10 6 Ibm/hr and rising.-11 SG Feed Flow is 3.5 x 10 6 Ibm/hr and lowering.What event is in progress?A.A S/G tube ruptured.B.The 11 FRV Bypass Valve failed open.C.A Turbine runback is in progress.A S/G PORV failed open.Justification:

A.Incorrect.

A tube rupture would not cause steam flow to increase.B.Incorrect.

The FRV bypass failing open would not cause stm flow to increase.C.Incorrect.

A runback would cause S/G level to decrease due to shrink D.Correct.S/G level increase due to swell, S/G pressure decrease due to increase in steam demand.Wednesday, March 10,201010:23:41 AM 52 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Know/edge of the effect of a loss or malfunction on the following will have on the S/GS: Secondary PORV Technical Reference(s):

B7-25, B8 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT.45 Obj 6b Question Source: Bank#_Modified Bank#---New X Question History: Last NRC Exam_--=N""'/c:...A"'--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:41 AM 53 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 31.038 EA1.44 001/038 EA1.44/3.4*/3.4/1/1!MIROININ/FINAL Given the following conditions:-1 E-3, Steam Generator Tube Rupture, is in progress.-11 S/G is ruptured.Subsequently the following conditions are observed:-11 S/G level indicates 2%NR with an AFW flow of 210 gpm.-12 S/G level indicates 1%NR with an AFW flow of 225 gpm.What is the operator response with regard to S/G water level control?A.AFW flow to 12 S/G can be isolated if desired.B.AFW flow to 11 S/G is required to be isolated at this time.C.AFW flow to BOTH S/Gs is required to be isolated when 11 S/G level rises above 5%NR.AFW flow to ONLY 11 S/G is required to be isolated when 11 S/G rises above 5%NR.Justification:

A.Incorrect.

S/G level is required to be maintained

>5%.B.Incorrect.

The ruptured S/G is required to be maintained

>5%to ensure a thermal layer exists above the tubes.C.Incorrect.

S/G level is being maintained 5%in intact S/Gs.Therefore, AFW flow to 12 SG is not required to be isolated.D.Correct.Per 1E-3, step 4.b Wednesday, March 10,201010:23:41 AM 54 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to operate and monitor the following as they apply to a SGTR: Level operating limits for S/Gs Technical Reference(s):

1 E-3 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-251 ATT.11 Obj 6 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_-:N.....,I"'-A"--

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:41 AM 55 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 32.039 K4.07 003/039 K4.07/3.4/3.7/2/lIMlRO/N/B/FINAL Given the following conditions:

-11 SG steam flow is 400,000 Ibm/hr.-12 SG steam flow is 600,000 Ibm/hr.-RCS Tavg is 520°F.-Containment Pressure is 0 psig.-RCS Pressure is 1750 psig.-Aux Building Fire Alarms are alarming.Which MSIV's have exceeded their automatic isolation setpoints?

A.BOTH 11 AND 12 MSIVs.ONLY 12 MSIV.C.ONLY 11 MSIV.D.NEITHER 11 OR 12 MSIV.Justification:

A.Incorrect.

Plausible if low RCS pressure SI (1830#), Hi stm flow (.505 x E6), and La-La Tave (540°F)setpoints are not recognized.

B.Correct.C.Incorrect.

Plausible if low RCS pressure SI (1830#), Hi stm flow (.505 x E6), and La-La Tave (540°F)setpoints are not recognized.

D.Incorrect.

Plausible if low RCS pressure SI (1830#), Hi stm flow (.505 x E6), and La-La Tave (540°F)setpoints are not recognized.

Wednesday, March 10,201010:23:41 AM 56 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following:

Reactor building isolation Technical Reference(s):

B18C Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-006 Obj 3 Question Source: Bank#P8180L-006042 Modified Bank#_New_Question History: Last NRC Exam_.....:N-"-A-=---

_QuestionCognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10,2010 10:23:41 AM 57 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 33.045 A3.11 002/045 A3.11/2.6*/2.9*/2/2/M/RO/N/NIFINAL Given the following conditions:-1 E-O, Reactor Trip or Safety Injection,;$in progress.-1 E-O, Attachment L is in progress.-8H16 and 8H17, Generator Output Breakers, are closed.What action is required?A.Manually OPEN 345KV Motor Operated Disconnects for breakers 8H16 and 8H17.B.Dispatch operators to locally OPEN Generator Output Breakers 8H16 and 8H17.Manually OPEN Generator Output Breakers 8H16 and 8H17 AND Generator Field Breaker.D.Manually initiate a Main Generator 86 Lockout.Justification:

A.Incorrect.

Plausible as opening MOD's would remove the generator from the grid, but MOD's are not designed to be opened under load.B.Incorrect.

Plausible as opening generator breakers locally would remove the generator from the grid, however this would not be performed unless it were not possible from the control room.e.Correct D.Incorrect.

Plausible as an 86 lockout is what the generator should have generated to open the breakers, but this action can not be performed manually..

Wednesday, March 10,201010:23:41 AM 58 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to monitor automatic operation of the MT/G system, including:

Generator trip Technical Reference(s): 1 E-O, Attachment L, Step 13 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT.24 Obj 2b Question Source: Bank#_Modified Bank#_New--,Xe..:.-

__Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10,201010:23:41 AM 59 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 34.054 AKl.OI 003/054 AKl.Ol/4.l/4.3/l/l/C/AIRO/N/N/FINAL Given the following conditions:

-Unit 2 is at 65%power.-Containment humidity is rising rapidly.-All Steam Generator Levels and Pressures are stable.-21 S/G Feed Regulating Valve is 80%open.Subsequently, a Containment Pressure SI signal is generated with the following conditions:

-21 S/G pressure is 600 psig and lowering.-22 S/G pressure is 800 psig and lowering.-RCS Cold Leg Temp is 520°F Upon completion of operator action, 22 TDAFW Pump will be_A.supplied steam from BOTH 21 AND 22 SGssupplied steam from 22 SG ONLY C.supplied steam from 21 SG ONLY D.unavailable Justification:

A.Incorrect.

Plausible if it is assumed S/G trends post trip are just normal variations in cooldown rate and given pressures are high enough in both SGs to supply the TOAFW Pump.B.Correct.C.Incorrect.

Plausible if initial conditions are confused and 22 S/G is assumed to be ruptured vice 21 having a feed leak.O.Incorrect.

Plausible if lowering pressure in both S/G is misdiagnosed to indicate both S/G are faulted.Wednesday, March 10,201010:23:42 AM 60 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break)Technical Reference(s):

2E-2 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-239 Obj B Question Source: Bank#_Modified Bank#---New---'X'-'--

__Question History: Last NRC Exam_-'N'-"I"'-A"--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41 8, 10 55.43__Comments: Wednesday, March 10,201010:23:42 AM 61 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 35.0552.2.44001/055 2.2.44/4.6/4.1/2/1/C/NROININIFINAL Given the following conditions:

-The conditions in the above photograph are seen on the control board.-A Unit 2 startup is in progress.-Condenser vacuum is being established.

-Condenser vacuum is 21 in.Hg.What operator action (if any)is required and why?A.No action is required until vacuum reaches 24.5 in.Hg.B.No action is required, vacuum is established with the given conditions.

C.Place Normal Service First Stage Jets in service to minimize air inleakage.Place Normal Service First Stage Jets in service to finish drawing vacuum.Wednesday, March 10,201010:23:44 AM 62 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM Justification:

A.Incorrect.

Plausible as 24.5 in.Hg.is the alarm for low vacuum in the ERCS system and required response is to place another ejector in service.B.Incorrect.

Plausible if student fails to recognize given indications or assumes vacuum is adequate.C.Incorrect.

Plausible as this is the correct action if it did NOT occur automatically, but increased vacuum results in increased air inleakage.

D.Correct.See Below This procedure is used to establish condenser vacuum during a unit startup.The normal service No.2 and No.3 air ejector second stage jets are placed in service first.When the condenser vacuum reaches 20 in.Hg., then the steam supply valve to the normal service first stage jets opens automatically.

If it is necessary to establish condenser vacuum more rapidly than is possible using the air ejector, then the hogger ejectors may be used.KIA Statement:

Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Technical Reference(s):

C26, 2C1.2 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8174L-001 Obj 3e Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 6,7 55.43 Comments: Wednesday, March 10, 2010 10:23:47 AM 63 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 36.055 EK1.02 001/055 EK1.02/4.1/1/I/C/AJRONIN/FINAL Given the following conditions:

-2ECA-0.O, Loss of All Safeguards AC Power, is in progress.-The Lead Operator performing the rapid depressurization of both SG's to 300 psig.-Pressure in both SG's reached 180 psig before the depressurization was stopped.What is the potential operational implication that could result from the excessive SG depressurization?

A.An integrity Red Path could be received due to the excessive RCS cooldown.B!'" Nitrogen injection from the accumulators may occur, interrupting natural circulation flow in the RCS.C.Low steam pressure may cause the TDAFW pump to trip on low discharge pressure, resulting in a loss of heat sink.D.Voiding may occur in the reactor vessel, causing the upper portion of the core to become uncovered and potentially causing fuel damage.Justification:

A.Incorrect.

The RCS must be cooled to near 200°F at low pressures to reach a RED path and SG saturation pressure is about 395°F, also transitions to FR procedures not made during ECA-O.O.B.Correct.Depressurization is designed to inject accumulators and excessive cooldown may result in nitrogen injection that could create a"hard" bubble in the SG's and degrade/stop natural circulation cooling.C.Incorrect.

The AFW pump discharge trip is bypassed by placing the selector switch in MANUAL.D.Incorrect.

Per the caution voiding is expected on the depressurization to 300 psig and it should not be stopped if it occurs.The voiding is expected during natural circulation in the upper head, but will not go lower than the RCS loop connections (well above the fuel)as natural circulation will collapse bubbles that make it into the loops.Wednesday, March 10,201010:23:47 AM 64 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the operational implications of the following concepts as they apply to the Station Blackout: Natural circulation cooling Technical Reference(s):

1 ECA-O.O Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-247, Objective 8 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_...:N...:.:/-'-A'-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43__Comments: Wednesday, March 10,201010:23:47 AM X 65 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 37.058 AA2.01 002/058 AA2.0l/3.7/4.l/1/l/C/AIRO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power.-11 Battery Charger trips on overload.-The Reactor trips SIMULTANEOUSLY.

________indicates that a loss of DC power has occurrred and restoration can be verified by_A"!Generator output breakers being closed, 47024-1201, 11 DC Panel Undervoltage, annunciator clearing B.Generator output breakers being closed, Blue Instrument Channel bistable status lights are LIT C.RCP Breakers Tripping, 47024-1201,11 DC Panel Undervoltage, annunciator clearing D.RCP Breakers Tripping, Blue Instrument Channel bistable status lights are LIT Justification:

A.Correct.B.Incorrect.

Plausible as generator output breakers will not open, but the instrument bus will swap power supplies and NOT be affected.C.Incorrect.

Plausibile as Bus 11 will temporarily lose control power, but this will not cause breakers to trip and the annunciator is accurate.D.Incorrect.

Plausible as Bus 11 will temporarily lose control power, but this will not cause breakers to trip and Blue instrument Channel will swap power supplies and NOT be affected.Wednesday, March 10, 2010 10:23:47 AM 66 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine and interpret the following as they apply to the Loss of DC Power: That a loss of dc power has occurred;verification that substitute power sources have come on line Technical Reference(s):

C47024-1201, 1 C20.9 AOP1, Proposed references to be provided to applicants during examination:

None Learning Objective:

P8186L-005 Obj 7.Question Source: Bank#--Modified Bank#_New--"X..:...-

__Question History: Last NRC Exam_...:Nc..:.:/"'-A.:.....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10,201010:23:47 AM 67 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 38.059 A3.06 001/059 A3.06/3.2/3.3/2/1/C/NROININIFINAL Given the following conditions:

-Unit 2 is at 100%power.-The reactor inadvertently trips.What will be the expected secondary plant response?A.S/G levels initially increase due to swell.Both MFW pumps will trip when Tave is less then 54rF.B.S/G levels initially decrease due to shrink.Both MFW pumps will trip when Tave is less then 554°F.c.S/G levels initially increase due to swell.Both Main Feed Regulating Valves close when Tave is less than 54rF.DY'S/G levels initially decrease due to shrink.Both Main Feed Regulating Valves close when Tave is less than 554°F.Justification:

A.Incorrect.

The listed SG level response is for a up-power not a down-power.

Both MFW pumps trip on a SI signal or on Hi-Hi SG levels, plausible if candidate confuses FRV and MFW pump responses.

Also 547"F islowlow tave setpoint, plausible if candidate confuses the low and thelowlow tave setpoints.

B.Incorrect.

The SG response is correct.Both MFW pumps trip on a SI signal or on Hi-Hi SG levels, plausible if candidate confuses FRV and MFW pump responses.

C.Incorrect.

The listed SG level response is for a up-power not a down-power.

547"F is low low tave set point, plausible if candidate confuses the low and the low low tave setpoints with the FRV response.D.Correct.Low Tavg 2/4, with Rx Trip Wednesday, March 10,201010:23:47 AM 68 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to monitor automatic operation of the MFW, including:

Feedwater isolation Technical Reference(s):

B7-27 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8170L-003B Obj 3 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_.....:N...:.:/..:-A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:47 AM X 69 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 39.059 AKl.Ol 002/059 AKl.Ol/2.7/3.l/l/2/M/RO/N/N/FINAL Given the following release types:1-Dissolved fission gases2-Beta-Gamma radiation3-Low level dissolved fission gases4-Delayed neutron and alpha radiation An accidental spill from the would result in a release of A'I Non-Aerated Sump Tank 1 and 2 B.Waste Holdup Tank 3 and 4 C.Volume Control Tank 1 and 4 D.Reactor Makeup Tank 1 and 2 Justification:

A.Correct.The Non-Aerated Sump Tank would not have fuel therefore no neutron or alpha radiation.

B.Incorrect.

Plausible as WHT recieves drains from floor drains, but would not have any delayed neutrons or alpha radiation without other accidents in progress.C.Incorrect.

Plausible as VCT collects the filtered Reactor Coolant, but without complicating accidents would not have any delayed neutron radiation.

D.Incorrect.

Plausible if RMU tank processing is not recognized as having removed all raditaion concerns.Wednesday, March 10,201010:23:47 AM 70 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant Technical Reference(s):

B21 B, B21 B-2 Proposed references to be provided to applicants during examination:

None Learning Objective:

FL-GAT-RWT-001L Obj RWT04&RWT05 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 13 55.43__Comments: Wednesday, March 10,201010:23:47 AM 71 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 40.059 K4.16 001/059 K4.16/3.1*/3.2*/2/l/M/RO/NIMIFINAL Unit 1 is at 100%power.What will cause only ONE Main Feed Pump to trip?A.12 SG level at 70%N.R.B.RCS pressure at 1770 psig.CY'11 Condensate Pump breaker trips.D.Feedwater pump suction pressure at 220 psig.Justification:

A.Incorrect.

2/3 SG levels>67%on either SG will trip both MFP's.B.Incorrect.

With RCS pressure at 1770 psig, a automatic SI would occur which would trip both MFWpumps.C.Correct.D.Incorrect.

Plausible since feedwater pumps suction pressure trip is actually 200 psig ,but condensate pumps auto start at 220 psig.An automatic feedwater pump trip signal is generated by anyone of the following conditions:

o Lube oilpressureless than 6 psig when the pump is operating.

o A turbine trip with both feedwater pumps operating on that unit (#11 and#21 pumps only)o Loss of 2/3 condensate pumps with both feedwater pumps operating on that unit (#11 and#21 pumps only).o Loss of all three condensate pumps on the associated unit.o Pump suction pressure less than 200 psig for greater than 5 seconds.The time delay allows time for the condensate bypass line valve to open and the standby condensate pump to start.o An undervoltage condition on the associated4.16KV bus for greater than 5 seconds.(1/2 coincidence

<75%).o A High-High level on either instrumentation train on either SG.(2/3>67%).o SI Wednesday, March 10,201010:23:47 AM 72 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following:

Automatic trips for MFW pumps Technical Reference(s):

B28A Proposed references to be provided to applicants during examination:

None Learning Objective:

P8174L-003 Obj 3 Question Source: Bank#_Modified Bank#__-,-P..=.8..:..17:.-4.:.,:L:;....;-O:...:O:...=3:.--1.:...;:6:o-New_Question History: Last NRC Exam_N/A_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10, 2010 10:23:47 AM 73 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 41.0612.4.18001l0612.4.18/3.3/4.0/2/1/MIRO/N/NIFINAL What is the basis for isolating Auxiliary Feedwater flow to the faulted steam generator with a feed line break?A.To minimize the CST level loss.B.To minimize the potential of rupturing a SG tube.C.To maximize the energy release from the faulted SG.To maximize the cooldown capability of the non-faulted SG.Justification:

A.Incorrect.

Plausible as CST inventory is preserved by securing this flow, but this is not the basis for this action.B.Incorrect.

Plausible as rupturing is a concern for re-initiation of AFVY, but is not a concern when securing.C.Incorrect.

Plausible if faulted and non-faulted S/G operations are confused.D.Correct.The temperature differential across the non-faulted S/G would increase when feedwater was isolated to a faulted S/G since they would be removing a larger decay heat load.KIA Statement:

Auxiliary Feedwater Knowledge of the specific bases for EOPs.Technical Reference(s):

1 E-2 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-239 Obj 7 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_.....:Nc..::/c:...A.:...-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content:

55.43__Comments: Wednesday, March 10,201010:23:47 AM 74 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 42.061 K5.05 001/061 K5.05/2.7/3.2/2/1/M/RO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power.-ERCS point 1T2871A, 12 MD AFWP DISC Temp is reading 180°F and slowly rising.-Turbine Building operator reports that the 12 MD AFW pump casing is too hot to touch.-Shift Supervisor enters C28.1 AOP1, STEAM BINDING OF AN AUXILIARY FEEDWATER PUMP.Which of the following is the required action(s)?

A.Close the affected pump discharge MOV's, start the pump and allow the pump to cool.B.Start the affected pump and allow the pump to cool, then vent the pump casing until a solid stream of water is observed.Close the discharge MOV's and allow pump to cool, then vent the pump casing until a solid stream of water is observed.D.Manually re-seat the affected pumps discharge MOV's and allow the pump to cool while monitoring pump casing and discharge temperatures.

Justification:

A.Incorrect.

While this would place the pump on recirculation and cool the pump it is not procedurally driven.B.Incorrect.

Pump is vented before starting.C.Correct.D.Incorrect.

Plausible since manually seating MOV's could reduce possible leakby but this would cause the MOV's to become inoperable.

Wednesday, March 10, 2010 10:23:47 AM 75 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the operational implications of the following concepts as the apply to the AFW: Feed line voiding and water hammer Technical Reference(s):

C28.1 AOP1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-007 Obj 4 Question Source: Bank#_Modified Bank#---New X Question History: LastNRCExam_-=Nc..:.:""-A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis10 CFR Part 55 Content: 55.41 5 55.43__Comments: Wednesday, March 10,201010:23:48 AM X 76 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 43.0622.4.8001/062 2.4.8/3.8/4.5/1/1/M/ROININIFINAL Given the following conditions:

-Unit 1 is at 100%power.-A Reactor trip and Safety Injection has occurred.-C47020-0204, Loop A Cooling Water Lo Press, is LIT.-C47520-0203, Loop A Cooling Water Lo Press, is LIT.-Loop"A" header pressure indicated 32 psig and lowering slowly.What describes the procedure flowpath and action?A.Perform 1 E-O, Reactor Trip and Safety Injection, AND C35 AOP1, Loss of Pumping Capacity or Supply Header with SI, concurrently.

B.Complete 1 E-O, Reactor Trip and Safety Injection, and THEN perform C35 AOP1, Loss of Pumping Capacity or Supply Header with SI.C.Perform only the immediate actions of 1 E-O, Reactor Trip or Safety Injection, and THEN perform C35 AOP1, Loss of Pumping Capacity or Supply Header with SI.Perform immediate actions of 1 E-O, Reactor Trip or Safety Injection, and THEN concurrently perform 1 E-O and C35 AOP1, Loss of Pumping Capacity or Supply Header with SI.Justification:

A.Incorrect.

Immediate actions of 1 E-O should always be performed first prior to performing actions of AOP's.Plausible since both procedures are required to be performed.

B.Incorrect.

Immediate actions of 1E-O should always be performed first prior to performing actions of AOP's.Plausible since both procedures are required to be performed.

C.Incorrect.

Immediate actions of 1E-O should always be performed first prior to performing actions of AOP's.Plausible since both procedures are required to be performed.

D.Correct.Wednesday, March 10,201010:23:48 AM 77 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KiA Statement:

Knowledge of how abnormal operating procedures are used in conjunction with EOP's.Technical Reference(s): 1 E-O I C35 AOP 1, SWI 0-10 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-251 ATT.14 Obj 7 Question Source: Bank#_Modified Bank#---New X Question History: Last NRC Exam_-:N...:.:/..:..A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10, 2010 10:23:48 AM 78 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 44.062 K2.01 001/062 K2.01/3.3/3.4/2/l/M/RO/N/BIFINAL Which of the following sets of EM panel power supplies is correct for the listed buses?1EMA 1EMB 2EMA 2EMB A'!Norm: INV 17 Alt: PNL 217 Alt: PNL 117 Norm: INV 28 B.Alt: PNL 217 Norm: INV 18 Norm: INV 27 Alt: PNL 217 C.Norm: INV 17 Alt: PNL 117 Alt: PNL 217 Norm: INV 28 D.Alt: PNL 217 Norm: INV 18 Norm: PNL 117 Alt: PNL 117 Justification:

A.Correct.B.Incorrect.

Plausible since power supply to 2EMB is the only part wrong.C.Incorrect.

Plausible since power supply to 1 EMB and 2EMA are the only parts wrong.D.Incorrect.

Plausible since power supply to 2EMA is the only part wrong.KIA Statement:

Knowledge of bus power supplies to the following:

Major system loads Technical Reference(s):

B20.8 Figures 8-5 and 8-6 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8186L-015 Obj.3 Question Source: Bank#P8186L-015 Modified Bank#_New---Question History: Last NRC Exam_.....

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments: Wednesday, March 10, 2010 10:23:48 AM 79 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 45.063 A2.01 001/063 A2.01/2.5/3.4/2/1/M/RO/Y/B/FINAL Given the following conditions:

-Unit 1 is at 100%power.-During maintenance on 11 DC Panel an electrical jumper causes the 125VDC POSITIVE BUS lead to GROUND.What is the result AND what is required NEXT?A':I C47024-1101, 11 DC PANEL GROUND DETECTION, is LIT.Dispatch an operator to locally investigate the alarm.B.C47024-1201, 11 DC PANEL UNDERVOLTAGE, is LIT.Check battery condition using ERCS display DC 1.C.Reactor Trip ONLY.Perform immediate actions of 1 E-O, Reactor Trip or Safety Injection.

D.Reactor Trip and Safety Injection.

Perform immediate actions of 1 E-O, Reactor Trip or Safety Injection.

Justification:

A.Correct.This is an ungrounded system, therefore a ground will only cause an Undervoltage on the affected side.Ground detection alarm will annunciate requiring the responding operator to dispatch the outplant operator to check the local panel for indications.

B.Incorrect.

This will not cause a panel undervoltage, only a voltage difference between the positive and negative sides of the bus.Plausible if operator does not understand the construction of the DC panel and the effect of the electrician's actions.C.Incorrect.

Plausible if the operator believes that the electrician's actions would lead to a loss of DC power on bus A which would cause a Reactor trip.D.Incorrect.

Plausible if the student believes that SI is deenergize to actuate.Wednesday, March 10,201010:23:48 AM 80 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to (a)predict the impacts of the following malfunctions or operations on the DC electrical systems;and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Grounds Technical Reference(s):

NF-40301-1, C47042-1101&

1201 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8186L-005, Objectives 5 Question Source:*Bank#P8186L-005 22 Modified Bank#_New_Question History: Last NRC Exam_...;2::.:0::.::0:..:.7,..,N..,.,R'->,C=-.:.R..:.:O:...::E::.:x=a.:.:.m,-

__Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43__Comments: Wednesday, March 10,201010:23:48 AM 81 2010 PRAIRIE ISLAND ILT NRC WRITIEN EXAM 46.063 A4.03 003/063 A4.03/3.0/3.1/2/l/C/NRO/N/N/FINAL Given the following conditions:

-The conditions in the above photograph are seen on ERCS.What describes the relationship between the Battery and the Battery Charger indicated on the above ERCS DC1 display?A.NEGATIVE amps indicate current flow OUT of the battery to the associated 480V Bus.NEGATIVE amps indicate current flow OUT of the battery to the DC Bus.C.POSITIVE amps indicate current flow OUT of the battery to the DC Bus.D.POSITIVE amps indicate current flow OUT of the battery to the associated 480V Bus.Wednesday, March 10,201010:23:48 AM 82 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM Justification:

A Incorrect.

Plausible as negative amps does indicate battery discharge, but this is not the appropriate flow path.B.Correct.C.Incorrect.

Plausible as positive amps would indicate flow of current between battery and the DC Bus, but not in the direction indicated.

D.Incorrect.

Plausible as positive amps would indicate flow between the battery and the 480V bus, but not in the direction indicated.

KIA Statement:

Ability to manually operate and/or monitor in the control room: Battery discharge rate Technical Reference(s):

B20.9 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8186L-005 Obj 5 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_-=N'-"/"'-A.:-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:49 AM X 83 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 47.0642.1.23001/0642.1.20/4.3/4.4/2/1/C/NRO/N/B/FINAL Given the following conditions:

-Unit 1 is in a normal electrical lineup.-01 Diesel Generator is loaded to 2600 KW during performance of SP 1295, 01 Diesel Generator 6 Month Fast Start Test.-The control room operator is adjusting load and voltage when the SPEED CONTROL switch sticks in the LOWER position and cannot be changed.What describes the FIRST action the operator should take?A'I Trip breaker 15-2, BUS 15 SOURCE FROM 01 DSL GEN B.Stop 01 using CS-46935, 01 DIESEL GENERATOR C.Direct the local operator to perform an emergency shutdown of 01.D.Trip breaker 15-3, BUS 15 SOURCE FROM 1 RY AUX XFMR Justification:

A.Correct.Removing DG from bus prior to any other action preserves safeguards power.B.Incorrect.

Action that would secure the DG, not procedurally driven.C.Incorrect.

Action that would secure the DG, not procedurally driven.D.Incorrect.

Action would isolate the bus, not procedurally driven KIA Statement:

Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Technical Reference(s):

SP1295, C20.7 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-222 Obj 3 Question Source: Bank#P8186L-00425 Modified Bank#_New---Question History: Last NRC Exam_..:..N.:.:.:/A'-'--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Comments: Wednesday, March 10,201010:23:49 AM 84 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 48.064 K6.07 001/064 K6.07/2.7/2.9/2/1/C/NRO/N/B/FINAL Given the following conditions:

-Unit 2 is at 100%power.-The Relief valve on D6 1A Starting Air Receiver has failed OPEN.-D6 Diesel Generator 1A Starting Air Receiver has been isolated.If a Unit 2 SI occurs, D6 Diesel Generator will.....A.NOT start.B.Start on Engine 2 ONLY and run on Engine 2 ONLY.C.Start on Engine 2 ONLY and run on BOTH engines.Start and run on BOTH engines.Justification:

A.Incorrect.

Plausible if student does not recogize that only one of the two starting air systems is needed to start both engines on 06.B.Incorrect.

Plausible if student does not recogize that only one of the two starting air systems is needed to start both engines on 06.C.Incorrect.

Plausible if student does not recogize that only one of the two starting air systems is needed to start both engines on 06.O.Correct.Each engine has two air systems feeding air distributors on respective sides of the engine, so both engines will receive starting air.(Note: "Start" means the air system operates to turn over the diesel,"run" means fuel is supplied to the cylinder to rotate the generator)

Wednesday, March 10, 2010 10:23:49 AM 85 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers Technical Reference(s):

B20.7 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8186L-014 Obj 3 Question Source: Bank#P8186L-01410 Modified Bank#_New_Question History: Last NRC Exam_--'N...:.:/..:...A"--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10, 2010 10:23:49 AM 86 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 49.065 AK3.08 003/065 AK3.08/3.7/3.9/1/1/C/AIRO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power.-11 Steam Generator tube rupture occurs.-The Instrument Air header is depressurized.-1 E-3, Steam Generator Tube Rupture, is in progress./'rf1A1f;5 The RCS cooldown iniate due to the opening of the_A.Condenser Steam Dump B.Atmospheric Steam DumpsSteam Generator PORVs D.Steam Generator Safety Valves.Justification:

A.Incorrect.

Plausible as this is the preferred method of cooldown, but is not available when instrument air is not available.

B.Incorrect.

Plausible if it is assumed the arming valves for the atmospheric dumps operate differently from the condenser steam dump.C.Correct.SG PORV are still operable due to an accumulator in line and it is directed to be operated locallyonthe intact SG per 1 E-3 step 7c RNO.D.Incorrect.

Plausible as the safety valves are not affected by the loss of air, but they are not the correct method of performing the cooldown.Wednesday, March 10, 2010 10:23:49 AM 87 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air ('Technical Reference(s):

1 E-3 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT.44 Question Source: Bank#_Modified Bank#_New X Question History: LastNRCExam_--'N"""':..:..A-'--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis10 CFR Part 55 Content: 55.41 5, 10 55.43__Comments: Wednesday, March 10,201010:23:49 AM X 88 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 50.068 A4.02 001/068 A4.02/3.2/3.1/2/2IM1RO/N/N/FINAL Given the following conditions:

-Unit 1 is at 100%power.-A 25 GPO tube leak in 11 Steam Generator has existed for the last 180 days.-Steam Generator Blowdown isalignedto the river for chemistry concerns with Radiation Protection Manager permission.

-1R-19, Steam Generator Blowdown radiation monitor goes intoHIGHalarm.

What are the expected control room indications that the release is terminated?

A.MV-32040&MV-32044,"A" STEAM GEN Bo ISOLATION VALVES, indicate CLOSED.11 Steam Generator Blowdown flow on recorder 42040 indicates ZERO.B:-" 11 and 12 Steam Generator Blowdown flows on recorder 42040 indicates ZERO.C.MV-32040&MV-32044,"A" STEAM GEN Bo ISOLATION VALVES, indicate CLOSED.MV-32043&MV-32058,"B" STEAM GEN Bo ISOLATION VALVES, indicate CLOSED.11 and 12 Steam Generator Blowdown flows on recorder 42040 indicate ZERO.O.CV-31414,"A" STM GEN Bo, hand controller indicates ZERO output.Justification:

A.Incorrect, Plausible because 11 SGB flow will be zero, but candidate may believe that the MV's close on high rad and CI.Candidate might think R19 is only associated with 11 SG.B.Correct, Both SGB CV will close on R19 Hi Rad, but hand controllers will still indicate demand ouput.The only indication in control room is the flow recorder.C.Incorrect, Plausible if candidate confuses MV closure signals D.Incorrect, Both SGB CV will close on R19 Hi Rad, but hand controllers will still indicate demand ouput.Plausible if student does not understand indication on hand controller and also thinks R19 is only associated with 11 SG.Wednesday, March 10,201010:23:49 AM 89 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to manually operate and/or monitor in the control room: Remote radwaste release Technical Reference(s):

1 C4 AOP2, B21 B Proposed references to be provided to applicants during examination:

None Learning Objective:

P8182L-002 3e Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_-'Nc..:.:/c:...A.:..-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content:

55.43 Comments: Wednesday, March 10, 2010 10:23:49 AM 90 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 51.073 Al.OI 002/073 Al.0l/3.2/3.5/2/I/M/RO/N/N/FINAL Given the following conditions:

-C21.3-10.1, Releasing Radioactive Gas From 121 Low Level Gas Decay Tank is in progress.-CV-31271, GAS DCY TNKS TO PLNTVNT,has been throttled.

-2R-30, Unit 2 Aux Building Vent Gas Monitor, and 2R-37, Unit 2 Aux Building Vent Gas Monitor, count rates begin to slowly rise.What is the LOWEST level at which the Operator is REQUIRED to terminate the release?A.When counts do NOT return to the previous stable value.When the expected value from the release permit is exceeded.C.When EITHER 2R-30 OR 2R-37 reach their alarm setpoints.

D.When BOTH 2R-30 AND 2R-37 reach their alarm setpoints.

Justification:

A.Incorrect.

Plausible if it is assumed the release rate has to be stable.B.Correct.The highest permissible value is the expected value on the release permit iaw C21.3-10.1 note prior to step 7.13.9.C.Incorrect.

Plausible as both 2R-30 and 2R37 will stop the release if their alarm setpoints are reached, but the release should be manually secured prior to this setpoint.D.Incorrect.

Plausible if is assumed their is redundancy of the securing indications.

Wednesday, March 10,201010:23:49 AM 91 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)associated with operating the PRM system controls including:

Radiation levels Technical Reference(s):

C21.3-1 0.1 Proposed references to be provided to applicants during examination:

none Learning Objective:

P8182L-001 C Obj 5 Question Source: Bank#_Modified Bank#_New

__Question History: Last NRC Exam_...:N....:.:/..:...A:..-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 13 55.43__Comments: Wednesday, March 10, 2010 10:23:49 AM 92 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 52.076 A2.01 001/076 A2.01/3.5/3.7/2/IIMJRO/N/BIFINAL Given the following conditions:

-Unit 1 and 2 are at 100%power.-"A" train cooling water flow is 7000 gpm.-"B" train cooling water flow is 6800 gpm.-47023-0603, SEISMIC MONITORING PANEL, is LIT.-EVENT ALARM is received on Seismic Monitoring Panel 121.-Floor vibrations are felt in the control room.-AB-3, Earthquakes is entered.-Subsequently, Safeguards bay level is 14 feet and lowering.What action is the crew required to perform NEXT?A.Reduce cooling water flow to less than 13,000 gpm.Trip BOTH reactors and enter 1 (2)E-0, Reactor Trip or Safety Injection.

C.Trip all 4 Circulating Water Pumps.D.Evaluate the earthquake severity per Attachment A.Justification:

A.Incorrect.

Plausible as this is the design limit for a single cooling water pump, but is not applicable in this casualty.B.Correct.C.Incorrect.

Plausible as this action is procedurally directed, but is not the NEXT action required.D.Incorrect.

Plausible as this action is procedurally directed, but is not the NEXT action required.Wednesday, March 10,201010:23:49 AM 93 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to (a)predict the impacts of the following malfunctions or operations on the SWS;and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of Service Water System Technical Reference(s):

AB3 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-231 Obj B.1 Question Source: Bank#P8176L-003 56 Modified Bank#---New_Question History: Last NRC Exam_....:.N...:,:/..:,..A.:.....-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:49 AM 94 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 53.076 AK3.05 001/076 AK3.05/2.9/3.6/l/2/C/A/RO/N/N/FINAL Given the following conditions:

-Unit 2 is at 100%power.-Chem Lab reports the RCS activity for Iodine 131 is 180 IJci/gm.-In-service demineralizer decontamination factor is 2.Information:

2R-9 (Reactor Coolant Letdown Line).2R-11 (CTMT/Shield Bldg Vent).2R-12 (CTMT/Shield Bldg Vent).What should be monitored and how can Iodine be removed?A'!Monitor 2R-9 and place the standby mixed bed demineralizer in service.B.Monitor 2R-11, 2R-12, and divert letdown to the hold up tank.C.Monitor 2R-9 and isolate normal letdown and place excess letdown in service.D.Monitor 2R-11, 2R-12, and place mixed beds and cation bed demineralizers in service.Justification:

A.Correct.2-R-9 monitors for high RCS activity;demin beds reduce RCS activity per references, see below.B.Incorrect.

R-11/12 monitors only during a gas release;hold up tank does not remove RCS activity.C.Incorrect.

Placing excess letdown in service will bypass the demineralizers.

D.Incorrect.

R-11/12 monitors only during a gas release.1.Have mixed bed demineralizer sampled both influent and effluent.2.IF decontamination factor for in-service demineralizer is less than 10, THEN shift to the standby mixed mixed bed demineralizer per C12.2, CVCS PURIFICATION AND CHEMICAL ADDITION Wednesday, March 10, 2010 10:23:50 AM 95 2010 PRAIRIE ISLAND ILT NRC WRITTEN EXAM KIA Statement:

Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity: Corrective actions as a result of high fission-product radioactivity level in the RCS Technical Reference(s):

C47047 2R-09 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8172L-001A Obj 5 AND P8182L-002 Obj 3a Question Source: Bank#_Modified Bank#_New--:.Xo..:...-

__Question History: Last NRC Exam_-=N...::/c.:...A"--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41---1L 55.43 Comments: Wednesday, March 10, 2010 10:23:50 AM x 96 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 54.078 A3.01 001/078 A3.01/3.1/3.2/2/1/M/RO/N/NIFINAL Given the following conditions:

-Both units are at 100%power.-The Instrument Air System is in a normal lineup.-Instrument Air Header Pressure decreases to 95 psig.What is the expected status of the system following the above event?A.One compressor is running loaded.Two compressors are running loaded.C.Three compressors are running loaded.D.Three compressors are running loaded AND MV-32318, SERVICE AIR HDR ISOL VLV, is CLOSED.Justification:

A.Incorrect.

Plausible if student confuses the many setpoints in the IA system B.Correct.C.Incorrect.

Plausible if student confuses the many setpoints in the IA system D.Incorrect.

Plausible if student confuses the many setpoints in the IA system KIA Statement:

Ability to monitor automatic operation of the lAS, including:

Air}pressure Technical Reference(s):

C34 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8178L-005 Obj 3e Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_.....:N...:,:/.:...A'--

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:50 AM 97 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 55.078 K3.02 001/078 K3.02/3.4/3.6/2/l/M/ROIN/B/FINAL The normal Instrument Air supply to 121 Control Room Chiller is isolated.121 Control Room Chiller is....A"!OPERABLE if the SUM of bottles A and B are above 2700 psig.B.NOT OPERABLE if EITHER bottle A or B drops below 2700 psig.C.OPERABLE if it remains running D.NOT OPERABLE if the chiller control air system is using the backup air supply.Justification:

A.Correct B.Incorrect.

Plausible as this is slightly above nominal full bottle pressure.C.Incorrect, Bottles must be filled if below 4000 psig.When filling commences the chiller is inoperable D.Incorrect, both bottles combined need to be above 4000 psig but not an operability issue.C37.11, step 5.2.3 C34 AOP 1, Attachment A KIA Statement:

Knowledge of the effect that a loss or malfunction of the lAS will have on the following:

Systems having pneumatic valves and controls Technical Reference(s):

C37.11, C34 AOP1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-0091 Obj 4 Question Source: Bank#P8178L-005007 Modified Bank#_New_Question History: Last NRC Exam_--'N'-"'c:...A-=---

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41_7_55.43 Comments: Wednesday.

March 10, 2010 10:23:50 AM 98 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 56.086 Al.OI 001/086 Al.01/2.9/3.3/2/2/C/A/RO/N/N/FINAL Given the following

-Unit 1 is at 100%power.-Fire header pressure drops to 94 psig.What is the fire protection system response to the pressure decrease?Jockey Pump MD Fire Pump Diesel Driven Fire Pump A.Running Standby Running B.Standby Running Standby C.Standby Standby RunningRunning Running Standby Justification:

A.Incorrect, Plausible as the Jockey pump is running, but motor driven and diesel driven start order has been reversed.B.Incorrect, Plausible as Jockey pump is not designed to provide flow, but would be running and other pumps status is accurate.C.Incorrect, Plausible as Jockey pump is not designed to provide flow, but would be running and motor driven and diesel driven start order has been reversed.D.Correct.Jockey Pump starts at 110 psig, MDFP starts at 98 psig, Diesel starts at 93 psig Conflicting numbers are given in F5 App K.and C31/B31A.Header Pressure of 94 psig has been selected to ensure Motor Driven is operating and Diesel Driven is NOT.Jockey Screenwash Motor Driven Diesel Driven F5 108-113 102 95 90 C31/B31A 110-115 106 98 93 Wednesday, March 10, 2010 10:23:50 AM 99 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)associated with Fire Protection System operating the controls including:

Fire header pressure Technical Reference(s):

F5 App K., B31A and C31 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8178L-002 Obj 4 Question Source: Bank#_Modified Bank#---New X Question History: Last NRC Exam_...:N...:.:/..:...A'--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10,201010:23:50 AM 100 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 57.103 Al.OI 0011103 Al.01l3.7/4.1I2/lIC/A/RO/N/N/FINAL Given the following plant conditions:

-Unit 1 is operating at 100%power.-Containment/Aux Building chillers are DOS for maintenance.

-CFCU's are on Cooling Water with an inlet temperature of 73°F.-Containment temperature is 9goF and slowly rising.-Containment pressure is 1.8 psig and slowly rising.-Containment humidity is 80%and slowly rising.What action is required to maintain containment within operating limits?A'I Place the post LOCA vent system in service to reduce containment pressure.B.Place the containment in-service purge system in-service to reduce pressure.C.Align all containment fan coil units to the dome to reduce temperature and humidity.D.Manually initiate Containment Spray to reduce containment temperature.

Justification:

A.Correct, Per C19.4 Post LOCA vent to be placed in service when containment pressure exceeds 1.3 psig.B.Incorrect, Plausible as this pressure over 1.3 psig is limitation mentioned in In-Service Purge system however it would not be appropriate to use it in this situation.

C.Incorrect, Plausible as this would remedy the situation give, but would remove cooling from operating RCP's.D.Incorrect, Plausible if the student misunderstands the given indications to indicate a LOCA and believes this action is warranted.

Wednesday, March 10, 2010 10:23:50 AM 101 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)associated with operating the Containment System controls including:

Containment pressure, temperature, and humidity Technical Reference(s):

C19.4 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-008 Obj 12a Question Source: Bank#--Modified Bank#_New X Question History: Last NRC Exam_-=N...;:/.;..A"--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41 9 55.43__Comments: Wednesday, March 10,201010:23:50 AM 102 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 58.2.1.29 OOl/2.1.29/4.l/4.0/3/MIRO/N/B/FINAL Given the follow conditions:

-An outplant operator is performing a system checklist.

-The outplant operator is required to THROTTLE open a manual valve five turns using a handwheel.

A second operator is required to perform during this evolution.

A.self checking B':I concurrent verification C.independent verification D.reference procedure usage Justification:

A.Incorrect.

Plausible as this is an error reduction technique, but not the one used in this instance.B.Correct.C.Incorrect.

Plausible as it is an independant operator, but this does not meet requirements of an independant verification.

D.Incorrect.

Plausible as using a second operator wouldfulfilthis function, but this is not a verification method.KIA Statement:

Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.Technical Reference(s):

FP-OP-COO-01 Proposed references to be provided to applicants during examination:

None Learning Objective:

P9150L-024 Obj 4 Question Source: Bank#P8140L-201 20 Modified Bank#_New_Question History: Last NRC Exam_N/A._QuestionCognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:50 AM x 103 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 59.2.1.41001/2.1.41/2.8/3.7/3/M/RO/NIB/FINAL Which of the following is a description of how a Rod Control Cluster Assembly (RCCA)is changed in a fuel assembly located inside containment?

A.1)manipulator removes the RCCA from the spent fuel assembly.2)places it in the basket of the change fixture.3)change fixture gripper picks up the RCCA.4)places it in the receiving fuel assembly in the upender.B.1)manipulator places a spent fuel assembly with an RCCA in one basket on the change fixture.2)change fixture gripper picks up the RCCA from the assembly.3)places it in the receiving fuel assembly in the upender.1)manipulator places a spent fuel assembly with an RCCA in one of the baskets on the change fixture.2)places the receiving fuel assembly in the basket next to the spent fuel assembly 3)change fixture gripper then picks up the RCCA.4)shifts it to the receiving fuel assembly.D.1)manipulator places a spent fuel assembly with an RCCA in one of the baskets on the change fixture.2)manipulator operator then removes the RCCA from the assembly with the manipulator.

3)places it in the receiving fuel assembly in the core.Justification:

A.Incorrect.

Inserts are not changed in the upender.It is physically possible to do this.B.Incorrect.

Inserts are not changed in the upender.It is physically possible to do this.C.Correct.D.Incorrect.

Inserts are not inserted in the core area.It is physically possible to do this.Wednesday, March 10,201010:23:50 AM 104 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the refueling process.Technical Reference(s):

C17 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8182L-003 Obj 2 Question Source: Bank#P8182L-003 70 Modified Bank#_New_Question History: Last NRC Exam_.....:N....:.;/..:.,.A.:-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 10 55.43_Comments: Wednesday, March 10,201010:23:50 AM 105 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 60.2.2.14 002/2.2.14/3.9/4.3/3fMIRO/NIB/FINAL While performing a checklist the Operator can initial in the initial box if_A'!the component status is the same as the status on the checklist AND there are NO safety tags on the component B.the component status is the same as the status on the checklist AND there IS a safety tag on the component AND the component is on the discrepency list C.the component status is NOT the same as the status on the checklist AND there are NO safety tags on the component, THEN reposition the component.

D.the component status is NOT the same as the status on the checklist AND there IS a safety tag on the component Justification:

A.Correct.Per C1.1 only if the component is in the same position and there are no tags can the checklist be initialed without further action.B.Incorrect.

Plausible as the component is in the required position and should be added to the discrepency list, however the step should not be signed off.C.Incorrect.

Plausible as the component is able to be repositioned it will be, but in such a case SS permission SHALL be obtained first.D.Incorrect.

Plausible if is assumed the tagged position of the component is an acceptable alternative to the status given by the checklist.

KIA Statement:

Knowledge of the process for controlling equipment configuration or status.Technical Reference(s):1C 1.1 pg 5-6 Proposed references to be provided to applicants during examination:

None Learning Objective:

P9150L-003 Obj.7 Question Source: Bank#P9150L-003007 Modified Bank#_New_Question History: Last NRC Exam_--'N..:,:/..:..,.A'--

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43_Comments: Wednesday, March 10,201010:23:50 AM 106 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 61.2.2.36002/2.2.36/3.1/4.2/3/M/RO/N/N/FINAL Given the following condition:

-Offsite OE was distributed indicating possible imminent failure of a component in 21 DC Battery Charger.-21 DC Battery Charger was removed from service for part replacement.

-The Portable Battery Charger has been installed to replace 21 DC Battery Charger.The Portable Battery Charger qualified backup equipment.

1.S.LCO 3.8.4.A is_is met B.is NOT met C.is NOT met D.is NOT NOT met Justification:

A.Correct.B.Incorrect.

Plausible as T.S.is met, but if examinee does not recognize the portable is qualified.

C.Incorrect.

Plausible if it is assumed the installed battery chargers are required even if the portable is qualified..D.Incorrect.

Plausible as T.S.would not be met if the portable were not qualified equipment.

Wednesday, March 10, 2010 10:23:50 AM 107 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

Technical Reference(s):

T.S 3.8.4 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8186L-005 Obj 10d Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_.....:Nc.::/c.:..A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41---1L 55.43__Comments: Wednesday, March 10,201010:23:51 AM X 108 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 62.2.2.6002/2.2.6/3.6/3.0/3/M/RO/NIM/FINAL Given the following conditions:

-Operators are performing an approved procedure on Unit 2.-Step 23 of the procedure has a Temporary Change Request (TCR).-The TCR is signed by the Unit 1 RO (first approver)and Unit 2 SS (second approver).

-The TCR has no other signatures or initials.-The TCR requires a flow rate greater than the Design Limit specified in the Precautions and Limitations Sections.Step 23 can NOT be performed_A'!because TCR's which change the intent or scope are NOT permitted.

B.until TWO Licensed Senior Reactor Operators view AND approve another TCR.C.because the TCR was not approved by personnel on the applicable unit.D.until a second Licensed Senior Reactor Operator counter signs the Unit 2 SS.Justification:

A.Correct.Changes to intent/design is not allowed.B.Incorrect.

Plausible if it is assumed the only problem is that the precautionllimitations section was not changed by the original TCR.C.Incorrect.

Plausible if it is assumed the only issues is the reviewers.

D.Incorrect.

Plausible if it is assumed that the same process to make emergency changes would be appropriate for using a TCR to continue a procedure.

Wednesday, March 10,201010:23:51 AM 109 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the process for making changes to procedures.

Technical Reference(s):

FP-G-DOC-04, Section 5.9, QF0013 Proposed references to be provided to applicants during examination:

None Learning Objective:

P9150L-003 Obj 9.Question Source: Bank#---Modified Bank#P9150L-003 9 New_QuestionHistory:Last NRC Exam_-:N....::/"-A"--

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:51 AM 110 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 63.2.3.11 002/2.3.1l/3.8/4.3/3/M/RO/N/B/FINAL When transferring contents of an ADT Monitor Tank, what design feature prevents the release of the contents to the discharge canal?At a MINIMUM,_A.ONE manual valve is maintained closed and locked B.ONE manual valve is maintained closed and locked and ONE control valve, interlocked with the radiation monitor R-18, WASTE LIQUID DISPOSAL LIQUID EFFLUENT MONITOR, is maintained closed.C.TWO manual valves are maintained closed and lockedTWO control valves in the release pathway are maintained closed with ONE of the valves locked and the other interlocked with the radiation monitor R-18, WASTE LIQUID DISPOSAL LIQUID EFFLUENT MONITOR Justification:

A.Incorrect.

Plausible as this is adequate isolation for a many liquid transfers.

B.Incorrect.

Plausible as their is a valve interlocked with R-18, but this is not the minimum requirement.

C.Incorrect.

Plausible as this is the appropriate isolation for high energy systems, but not the procedural method for ADT tank transfers.

D.Correct.CV-31256 (RCV-018), Waste Liquid Common Discharge Header Valve, which is interlocked to close on high radiation sensed by RE-18, AND CV-31841, Waste Liquid Common Discharge Header Keylock Release Valve, are maintained closed with CV-31841 locked, during all operations not involving a liquid release.Wednesday, March 10, 2010 10:23:51 AM 111 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to control radiation releases Technical Reference(s):

C21.1.1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8182L-001A Obj 4 Question Source: Bank#P8182L-001A 001 Modified Bank#_New_Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 13 55.43__Comments: Wednesday, March 10,201010:23:51 AM 112 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 64.2.3.14 003/2.3.14/3.4/3.8/3/M/ROININ/FINAL Given the following conditions:

-Refueling is in progress.-A spent fuel element is being moved from the reactor to the upender.-The spent fuel element is dropped to the bottom of the canal and ruptures.What products released from the ruptured spent fuel element will present the MOST immediate hazard?A.Hydrogen gas.B.Gamma radiation from activated Nitrogen.C.Gamma radiation from corrosion products.Gamma radiation from Iodine and Krypton gases.Justification:

A.Incorrect.

Plausible as hydrogen is a hazardous chemical present in fuel, but is not the present hazard.B.Incorrect.

Plausible as this is one of the major concerns for reactor coolant, but in the absence of fission there should not be a significant source.C.Incorrect.

Plausible as this is an appopriate hazard, but not outside of the fuel cell.D.Correct.KIA Statement:

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Technical Reference(s):

USAR Section 14F HA Proposed references to be provided to applicants during examination:

None Learning Objective:

P8182L-003 Obj 3c Question Source: Bank#_Modified Bank#_New X Question History: LastNRCExam_--:.N...:.:c/.:....A=--

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41-1.L 55.43 Comments: Wednesday, March 10, 2010 10:23:51 AM 113 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 65.2.4.2 00 l/2.4.2/3.9/4.l/3/C/A/ROINIBIFINAL Given the following conditions:-A Unit 1 startup is in progress per1C 1.2, Unit 1 Startup Procedure.

-Reactor power is 6%and stable.-The RO withdraws rods one step.-Rods continue to step OUT, AFTER the RO releases the switch.-Reactor power reaches 28%prior to a MANUAL reactor trip.-1 E-O, Reactor Trip or Safety Injection, is entered.An automatic reactor trip should occurred due to----------------------

A.NOT have, Intermediate Range High Flux Trip being manually blocked per procedure at the initial power level B.have, P-7 enabling'at power trips'when power exceeded the setpoint C.NOT have, Power Range Trip-Low Setpoint trip setpoint NOT being reachedhave, Power Range Trip-Low Setpoint trip setpoint being exceeded.Justification:

A.Incorrect.

Plausible as this trip would be blocked>10%(P-10), however under these conditions that action would not have taken place.B.Incorrect.

Although at-power trips automatically enabled they are not NIS power trips.C.Incorrect.

Setpoint is 25%and is exceeded.D.Correct.Setpoint 25%and requires manual action to block.IR trip setpoint also would give trip but this option is not presented.

Wednesday, March 10,201010:23:51 AM 114 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Note: The issue of setpoints and automatic safety features is not specifically covered in the systems sections Technical Reference(s):

1 C1.2 section 5.14, B-8 table B8-1, B8-2 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8184L-004 Obj 7 Question Source: Bank#P8184L-004 59 Modified Bank#---New_Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content 55.41 7 55.43__Comments: Wednesday, March 10,201010:23:51 AM 115 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 66.2.4.42 00 l/2.4.4212.6/3.8/3/MJROININ/FINAL A General Emergency has been declared.All of the facilities

/centers are fully staffed.Which of the following coordinate the OFFSITE radiological monitoring during emergencies and recovery operations?

A.Control Room.8.Technical Support Center.Emergency Operating Facility.D.Operations Support Center.Justification:

A.Incorrect.

Plausible as the control direct most activities, but not the one listed.B.Incorrect.

Plausible as the TSC coordinates inplant radiological monitoring.

C.Correct.After the EOF is staffed, the responsibility is passed to the EOF.D.Incorrect.

Plausible as the OSC will deploy the required personnel in the plant.KIA Statement:

Knowledge of emergency response facilities.

Technical Reference(s):

F3 Proposed references to be provided to applicants during examination:

None Learning Objective:

P7405L-001 Obj 3 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_-=N...:.:/.:..A.:..-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:51 AM 116 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 67.2.4.600l/2.4.6/3.1/4.0/3/MIRO/N/B/FINAL During which set of conditions below is it appropriate to use 1 ES-O.O, Rediagnosis?

During performance of...A.1 FR-S.1, Response to Nuclear Generation/ATWS, AND the reactor is locally tripped.B.1 E-O, Reactor Trip or Safety Injection, when diagnosis steps are completed AND the cause of the SI has NOT been determined.

C'l'" 1 E-1, Response to Loss of Reactor or Secondary Coolant, when operators are unsure if they are in the correct procedure.

D.1 ECA-O.O, Loss of All AC Power, when a steam generator begins to depressurize in an uncontrolled manner AND has NOT been isolated.Justification:

A.Incorrect.

1 FR-S.1 contains steps to verify reactor trip has occurred and transition back to 1 E-O.B.Incorrect.

1 E-O diagnosis will continue until the appropriate procedure is selected or SI termination criteria is reached.Entry criteria for 1 ES-O.0 is not met until a transition has been made from 1 E-O to another 1 E-series procedure.

C.Correct.Per 1 ES-O.0 entry conditions.

D.Incorrect.

ECA-O.O is not transitioned from until directed and per entry conditions 1 ECA-O.0 is not an E-series procedure which allows use of 1ES-0.0.KIA Statement:

Knowledge of symptom based EOP mitigation strategies Technical Reference(s):

1 ES-O.O Proposed references to be provided to applicants during examination:

None Learning Objective:

P8197L-011 Obj B1 Question Source: Bank#P8197L-011 74 Modified Bank#_New_Question History: Last NRC Exam_-=2:;..;:0,-=0.....:.4_Ro....:.=O.....:.N...:.,:R...o.C=--:;:E:.;..XA.:;.....;.:.;M,-,--_

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:51 AM 117 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM 68.E04 EK2.2 002/E04 EK2.2/3.8/4.0/l/1/C/A/RO/N/N/FINAL Given thefollowingconditions:

-Unit 1 is at 100%power.-A LOCA Outside Containment occurs and can NOT be isolated.As a result, Transfer to Recirculation occur due to----------A.will, Sump B being filled from RHR pit drains B.will, using Containment Spray pumps to fill Sump Bwill NOT, Sump B being empty D.will NOT, radiological concerns in the auxiliary building Justification:

A.Incorrect.

Plausible as Sump B drains are pumped to containment to recover water, but these drains are not adequate to fill sump B..B.Incorrect.

Plausible as Containment Spray pumps would add significant water to Sump B, but this action is not procedurally directed.C.Correct.D.Incorrect.

Plausible if radiological concerns are severe enough to prevent performance of Aft.K actions to align for recirc however these actions are not required to go to recirc.Wednesday, March 10, 2010 10:23:51 AM 118 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the interrelations between the LOCA Outside Containment and the following:

Facility's heat removal systems, including primary coolant, emergency coolant, decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.Technical Reference(s):

1 ES-1.2, 1 E-1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8197L-012 Obj 22.Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41_7_55.43__Comments: Wednesday, March 10,201010:23:51 AM 119 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 69.E05 2.1.7 002/E05 2.1.7/4.4/4.7/l/l/C/AIRO/N/NIFINAL Given the following conditions:-A Large Break LOCA has occurred.-1 E-1, Loss of Reactor or Secondary Coolant, is in progress.-AFW flow can not be established.

-All SG NR levels are off-scale low.-The crew enters 1 FR-H.1, Response to Loss of Secondary Heat Sink.The following is observed:-RCS Pressure is 25 psig and slowly lowering.-Intact SG pressures are 475 psig and lowering.Steam Generators are because_A.required, a secondary heat sink is required B.required, S/G tubes must be covered to avoid damage.C.NOT required, reintroduction of AFW would cause damage.NOT required, decay heat is NOT being transferred to the S/Gs.Justification:

A.Incorrect.

Plausible as many LOCA situations require Secondary heat sink, however secondary heat sink is not required if SGs are at a higher pressure than the RCS.They act as a heat source.B.Incorrect.

Plausible as many LOCA situations require Secondary heat sink, however secondary heat sink is not required if SGs are at a higher pressure than the RCS and under other circumstances maintaining the S/G tubes covered is relevant.C.Incorrect.

Plausible as S/Gs are NOT required, because RCS pressure is below SG pressure and reintroducation of AFW to a hot, dry S/G can cause damage.D.Correct.Wednesday, March 10,201010:23:51 AM 120 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Technical Reference(s):

1 E-1, 1 FR-H.1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8197L-014 Obj 25 Question Source: Bank#_Modified Bank#_New-'X'-'--__Question History: Last NRC Exam_-=N....:.:/'"'-A-=--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43__Comments: Wednesday, March 10,201010:23:51 AM x 121 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 70.E06 EA2.2 003IE06 EA2.2/3.6/3.8/l/2/MIROINIB/FINAL Given the following conditions:

-Unit 1 LOCA, is in progress.-The crew is in 1 FR-C.1,"Inadequate Core Cooling".The RO observes the following conditions:

-RCS Pressure is 475 psig and slowly lowering.-RVLlS Full Range is 35%and lowering..-CETC Temp is 1300°F and rising.-RCS Hot Leg Temp is 450°F and rising.-Both RCPs are stopped.-Both SG WR levels are 52%WR and stable.-4.16KV Safeguards Bus 15 is Locked Out.-12 SI pump is OOS for maintenance.

-12 RHR pump tripped on overload.Which of the following is true regarding RCPs?A.RCPs are started to force water inventory from the pressurizer into the core to collapse possible voids in the upper head region.RCPs are started to provide temporary cooling of the RCS until makeup flow can be established.

C.RCPs are left OFF to preventdamagingthe pumps because of low seal differential pressures.

D.RCPs are left OFF to limit their heat input into the core which could challenge core cooling.Justification:

A.Incorrect.

Plausible as voids exist in the given condition, but void collapse is not the purpose of starting the RCPs.B.Correct.Per FR-C.1.C.Incorrect.

Plausible as pump damage is likely, but not a concern for the given situation.

D.Incorrect.

Plausible as pumps are a considerable heat source, but not in this situation.

Wednesday, March 10,201010:23:52 AM 122 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM KIA Statement:

Knowledge of the interrelations between the Inadequate Core Cooling and the following:

RCP Technical Reference(s):

1 FR-C.1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8197L-014 Obj 16 Question Source: Bank#P8197L-014139 Modified Bank#_New_Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content 55.41 7 55.43__Comments: Wednesday, March 10, 2010 10:23:52 AM x 123 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 71.ElO EK2.2 OOl/ElO EK2.2/3.6/3.8/1/2/M/RO/N/B/FINAL 2ES-0.4, Natural circulation cooldown with steam voids in the vessel, is in progress.RVLlS full range level is maintained greater than 82%to...A.maintain adequate core cooling by keeping the fuel covered.B.keep the core exit thermocouples covered for an accurate indication of subcooling.prevent disrupting natural circulation flow due to voids entering the hot legs.D.prevent a water solid condition in the pressurizer which would result in a loss of pressure control.Justification:

A.Incorrect.

Pluasible as this is the normal function of RVLlS, but not in this situation.

B.Incorrect.

Plausible as this is an effect of maintaining RVLlS level, but is not the bases.C.Correct D.Incorrect.

Plausible as this is the normal method of pressure control, but not with given conditions.

KIA Statement:

Knowledge of the interrelations between the Natural Circulation with Steam Void in Vessel with/without RVLlS and the following:

Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility Technical Reference(s):

2ES-0.4 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8197L-011, Obj E Question Source: Bank#P8197L-011 061 Modified Bank#_New_Question History: Last NRC Exam_-'N...:.:/..:...A::..-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10, 2010 10:23:52 AM 124 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 72.Ell EK3.3 002/Ell EK3.3/3.8/3.8/1/1/C/AIROIN/M/FINAL Given the following conditions:-A Large break LOCA has occurred.-Attempts to place ECCS in recirculation have failed as Sump B valves failed to OPEN.-1 ECA-1.1, Loss of Emergency Coolant Recirculation, is being performed.

-Step 5, Determine Containment Spray Requirements, is in progress..What is the reason for the manipulation of the Containment Spray pumps?A.To provide for a quicker reduction in containment pressure.To minimize Containment Spray operation to conserve RWST level.C.To minimize Containment Spray pump operation while increasing ECCS flow.D.To minimize the number of Fan Coil Units operating while increasing Containment Spray pump operation.

Justification:

A.Incorrect.

Plausible if purpose of this step is not understood.

B.Correct.This step evaulate for the minimum required Containment Spray pumps to conserve available RWST water.C.Incorrect.

Plausible if it assumed that lowering the running Containment Spray pumps will enable increased ECCS Flow.D.Incorrect.

Plausible if it assumed the goal is to trade running CFCU's for Containment Spray pUrTJPs.Wednesday, March 10, 2010 10:23:52 AM 125 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM KIA Statement:

Knowledge of the reasons for the following responses as they apply to the Loss of Emergency Coolant Recirculation:

Manipulation of controls to obtain desired operating results during abnormal, and emergency situations.

Technical Reference(s):

1 ECA-1.1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8197L-012 Obj 24 Question Source: Bank#---Modified Bank#_-,-P-=8o...:.1-=.9..:...,:7L=---=.0..:..:12=---:1....,:.4-=.3

__New_Question History: Last NRC Exam_-:N....:,;/..:-A"-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5.10 55.43__Comments: Wednesday, March 10,201010:23:52 AM 126 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM 73.E12 EK3.1 003/E12 EK3.1/3.5/3.9/1/1/C/AIRO/N/NIFINAL Given the following conditions:

-Unit 1 was at 100%power.-A large steam line break on the common steam header occurred.-Reactor trip and Safety Injection actuate.-NONE of the MSIVs closed automatically.

With NO operator action, AFTER the initial decrease RCS pressure will_A.stabilize at a lower RCS pressure B.rise AND stabilize at SI pump shutoff head C.rise AND stabilize at normal RCS pressure (2235 psig)rise AND cycle at Pressurizer PORV pressure (2335 psig)Justification:

A.Incorrect.

Plausible if is assumed AFW can remove enough heat to maintain low pressure.B.Incorrect.

Plausible if charging pumps effect are not recognized and it is assumed SI pumps are the only source of injection.

C.Incorrect.

Plausible if it is assumed normal pressurizer spray is able to compensate.

D.Correct.With SI and no break in the RCS eventually the RCS will be cycling on the PORVs.KIA Statement:

Knowledge of the reasons for the following responses as they apply to the (Uncontrolled Depressurization of all Steam Generators)

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.

Technical Reference(s):

1 ECA-2.1 Basis Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 ATT.40 Obj 5a Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_-'N...:.:/..:...A.:.....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43__Comments: Wednesday, March 10,201010:23:52 AM X 127 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 74.E13 EK2.1 004/E13 EK2.l/3.0/3.l/l/2IM1RO/NIBIFINAL Given thefollowingconditions:

-FR-H.2, Response to Steam Generator Overpressure, is in progress.Steam Generator overpressure condition exists when SG pressure exceeds__because this is above the setpoint.A.1050, SG PORV controller B.1050, highest SG safety C.1131, SG PORV controller1131, highest SG safety Justification:

.A.Incorrect.

Plausible if exceeding PORV setpoint is assumed to constitute an overpressure condition.

B.Incorrect.

Plausible if as the highest safety setpoint being ecxeeded is the condition that constitutes overpressure, however this is not the setpoint for the highest safety setpoint.C.Incorrect.

Plausible as this is the correct pressure value that would constitute an overpressure condition, but this is not the setpoint for the SG PORV controller.

D.Correct.This is the applicable criteria for the overpressure condition and the appropriate piece of equipment.

Wednesday, March 10, 2010 10:23:52 AM 128 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the interrelations between the (Steam Generator Overpressure) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.Technical Reference(s):

1 FR-H.2 Proposed references to be provided to applicants during examination:

None Learning Objective:

Question Source: Bank#P8197L-014-171 Modified Bank#_New_Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43__Comments: Wednesday, March 10, 2010 10:23:52 AM 129 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 75.E16 EA2.2 OOl/E16 EA2.2/3.0/3.3/2/1/M1ROINIB/FINAL Given the following plant conditions:-A LOCA has occurred.-The crew is performing cooldown as directed by 1 ES-1.2, Post LOCA Cooldown and Depressurization.

-ECCS pumps are operating in injection mode.-Containment Spray has been stopped.-TWO CFCU's are running.-Containment pressure is stable at 2.2 psig.-The Shift Supervisor transitions to 1 FR-Z.3, Response to High Containment Radiation Level, in response to a YELLOW Critical Safety Function Status Tree.What action directed in 1 FR-Z.3 will help to reduce containment radiation levels due to fission product gases?A.Initiate flow through the Containment Post-LOCA Hydrogen Control System.B.Start the idle Containment Fan Coil Units.Place Containment Cleanup Fans in service.D.Initiate Containment Spray.Justification:

A.Incorrect, Not effective for rad levels.B.Incorrect, Not effective for rad levels.C.Correct.D.Incorrect, Would unnecessarily spray down containment after securing, CS only effective for removing iodines.Wednesday, March 10,201010:23:52 AM 130 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine and interpret the following as they apply to the (High Containment Radiation):

Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Technical Reference(s):

1 FR-Z.3 Proposed references tobeprovided to applicants during examination:

None Learning Objective:

P8197L-014 Obj 42 Question Source: Bank#P8197L-014 87 Modified Bank#_New_Question History: Last NRC Exam_....:N..:,,/"'-A"--

_QuestionCognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41 10 55.43__Comments: Wednesday, March 10,201010:23:52 AM 131 c 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 76.S 003 2.4.45 001/003 2.4.45/4.1/4.3I2/l/C/A/SROfN/B/RFI Given the following conditions:

-Unit 2 at 100%power and stable.-47519-0403, 23 Containment Fan Coil Unit Motor Stator HI Temp, is LIT.-23 CFCU breaker has tripped on overload.-47521-0605, Reactor Gap Cooling LO Flow, is LIT.-47515-0506,21 RCP Bearing/Stator HI Temp, is LIT-21 RCP Stator temperature is 305°F and slowly rising.-47512-0203,21 or 22 RCP HI Vibration, is LIT.-21 RCP Shaft vibration is 11 mils and rising.To place the plant in a safe condition, the SS will direct the RO to perform_A.C47512-0203, 21 or 22 RCP HI Vibration B.C47521-0605, Reactor Gap Cooling LO FlowC47515-0506, 21 RCP Bearing/Stator HI Temp D.C47519-0403, 23 Containment Fan Coil Unit Motor Stator HI Temp Justification:

A.Incorrect.

Plausible as this would satisfy the general convention of picking the lowest number alarm first, however this alarm will not place the plant in a safe condition.

B.Incorrect.

Plausible as this alarm will result in restoration of gap cooling the fastest, but this will not place the plant in a safe condition.

C.Correct.This alarm will address the high temperature on the stator and will direct the tripping of the reactor to place the plant in a safe condition.

D.Incorrect.

Plausible as under general conditions you would start with the initiating alarm response, but this ARP will not result in the plant being in a safe condition.

Wednesday, March 10, 2010 10:23:52 AM 132 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Rep, Ability to prioritize and interpret the significance of each annunciator or alarm.Technical Reference(s):

47512-0203 Proposed references to be provided to applicants during examination:

None Learning Objective:

P81070L-002 Obj 3 Question Source: Bank#_Modified Bank#_New

__Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content:

55.43_5_Comments: Wednesday, March 10,201010:23:52 AM 133 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 77.S 012 A2.06 002/012 A2.06/4.4/4.712/l/C/AiSRO/N/NIFINAL Given the following conditions:

-Unit 1 is at 100%power and stable.-47017-0202, PRZR LO Press Reactor Trip, is LIT.-The Reactor fails to automatically trip.-ALL attempts to trip the Reactor from the control room FAIL.-The Turbine Building Operator opens the Reactor Trip Breakers locally.-R-9, Reactor Coolant Letdown Line Radiation Monitor, reads 2R/hr.What, if any, EAL is the Shift Supervisor required to declare?A.None B.Unusual Event C.AlertSite Area Emergency Justification:

A Incorrect.

Plausible if it is assumed that since the corrective actions have been taken the declaration is no longer required.B Incorrect.

Plausible as SU4.1 is met and this is the only one recognized.

C Incorrect.

Plausible as the high level step only mentions manual trip being successful and this does not include manual local action.D.Correct.SS2.1 is applicable when local manual action is required to open the Reactor Trip breakers.Wednesday, March 10,201010:23:52 AM 134 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM KIA Statement:

Ability to (a)predict the impacts of the following malfunctions or operations on the RPS;and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of RPS signal to trip the reactor Technical Reference(s):

F3-2, F3-2.1 Bases.Proposed references to be provided to applicants during examination:

F3-2, EAL Charts.Learning Objective:

P7410L-034 Obj 10 Question Source: Bank#--Modified Bank#_New----"'"X'->--

__Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41 Comments: Wednesday, March 10,201010:23:52 AM 135 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM 78.S 008 2.1.20 003/008 2.1.20/4.6/4.6/2/1/C/A/SRO/N/N/RFI Given the following conditions:-1 ES-1.1, Post LOCA Cooldown and Depressurization, is in progress.-The Crew is starting Step 22, Check if RCP Seal Return flow should be established.-1 R-48, U1 CNTMT HI RNG AREA MaN B, is reading 300 R/hr.-1 R-49, U1 CNTMT HI RNG AREA MaN A, is reading 300 R/hr.To restore Component Cooling (CC)flow to the Seal Water Heat exchanger____CC HX crossover valve(s)is(are)required to be opened.The SRO__direct RCP Seal Return Isolation Valves to be opened.A'I EITHER Train A OR Train B, will NOT B.Train A, will C.Train B, will D.BOTH Train A AND Train B, will NOT Justification:

A.Correct.Either train can supply the SealWaterHeat Exchanger and with given radioactivity the Rep seal injection will not be restored.B.Incorrect.

Plausible as most systems have unit specific trains, though CC system is not one of them.With given RCS activity RCP seal injection will not be restored.C.Incorrect.

Plausible as most systems have unit specific trains, though CC system is not one of them.With given RCS activity RCP seal injection will not be restored.D.Incorrect.

Plausible if it assumed both valves must be opened to restore flow and with given radioactivity the RCP seal injection will not be restored.In this step of 1 ES-1.1 the SRO must determine if the RCP Seal injection should be restored.The step itself does not include any radiation checks, however the basis for the step discusses NOT restoring the flow if activities are high as this would bring high activity water into the VCT/Aux Building.With the given conditions the SRO will not restore RCP seal return to avoid this radiation hazard.Wednesday, March 10,201010:23:53 AM 136 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Component Cooling Water: Ability to interpret and execute procedure steps.Technical Reference(s):

1 ES-1.1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 Att.34 Obj 5 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41_1:..:::.0_

55.43 4,5 Comments: Wednesday, March 10, 2010 10:23:53 AM X 137 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 79.S 009 EA2.01 003/009 EA2.0l/4.2/4.8/l/l/C/A/SROfNIM/RFI Given the following conditions:-A small break LOCA has occurred on Unit 1.-11 SI pump has been stopped as directed in 1 ES-1.1, Post LOCA Coo/down and Depressurization.

Subsequently the Reactor Operator notes the following:

-RCS subcooling is-2°F.-RCS pressure is 1050 psig and decreasing.

-Pressurizer level is 25%and decreasing.

-Containment pressure is 7 psig and stable.-SG levels indicate 5%NR (49%WR)on BOTH SGs and stable.-Total AFW flow is 250 gpm.-ONE Charging Pump is running at maximum speed.-RVLlS is 50%Dynamic Range with one RCP running.The Shift Supervisor will direct the crew to AND_A.increase RCS cooldown rate, remain in 1 ES-1.1, Post LOCA Cooldown and Depressurization B.manually actuate Safety Injection, transition to 1 E-1, Loss of Reactor or Secondary Coolant Clf'manually start the stopped Safety Injection Pump, remain in 1 ES-1.1, Post LOCA Cooldown and Depressurization D.manually actuate Safety Injection, transition to FR-C.2 Response to Degraded Core Cooling Justification:

A.Incorrect.

Plausible as this will correct the issue with subcooling, but is not procedurally directed.B.Incorrect.

Plausible as SI is required, however it should not be initiated by actuating SI and 1 E-1 is the appropriate procedure for the given situation, but is not re-entered.

C.Correct.D.Incorrect.

Plausible as SI is required, however it should not be initiated by actuating SI, and though FR-C.2 has appropriate actions to raise subcooling it's entry conditions are not met.Per the Information Page, SI Reinitiation Criteria is met with ADVERSE containment conditions for inability to maintain przr level>27%.Other choices are steps in the ES procedure or transitions to other procedures.

Wednesday, March 10,201010:23:53 AM 138 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine or interpret the following as they apply to a small break LOCA: Actions to be taken, based on RCS temperature and pressure, saturated and superheated Technical Reference(s):

1ES-1.1 info page Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 Atl.34 Obj 5 Question Source: Bank#Modified Bank#_-,-P....,:8,,-,1..::.9-,-,7L=--..::.O....:.:12=-..:....74....:.-_

New_Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41__55.43_5_Comments: Wednesday, March 10, 2010 10:23:53 AM 139 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 80.SOil A2.10 00l/011 A2.10/3.4/3.6/2/2/C/A/SRO/N/NIRFI Given the following conditions:

-Unit 1 is at 100%power.-11 Charging Pump is in automatic.

-12 Charging Pump is in manual.-1L T-426 (Red)Pressurizer level transmitter was removed from service yesterday.-1 L1-427 (White)Pressurizer level is 20%and lowering.-1 L1-428 (Blue)Pressurizer level is 91%and slowly rising.-11 Charging Pump speed is lowering.-1 FI-128, Charging Flow to Regen HX, is lowering.What action is the Shift Supervisor required to direct?A.Take manual control of 11 Charging Pump and minimize charging flow per C47012-0307, PRZR HI Lvi Channel Alert.B.Take manual control of 11 Charging Pump and maximize charging flow per C47012-0507, PRZR Level Deviation.

C.Remove the blue channel from service per 1 C51.3, Instrument Failure Guide.D'!'" Manually trip the reactor and enter 1 E-O, Reactor trip and Safety Injection.

Justification:

A.Incorrect.

Plausible if the high level is assumed to be the accurate level and manually action is desired to correct it.B.Incorrect.

Plausible if the failed blue channel is correctly diagnosed, but trip criteria is not recognized.

This action would be appropriate to recover the actual low level in the przr.e.Incorrect.

Plausible as this action is appropriate if the trip criteria is not recognized, but this action would cause a reactor trip upon performance of C51 steps.D.Correct.With the given information Blue channel is failed and with a second failed channel the reactor must be tripped due to 2/3 logic satisfied for>90%Pressurizer Level.An automatic trip should have occurred with these conditions.

Wednesday, March 10,201010:23:53 AM 140 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Failure of PZR level instrument

-high Technical Reference(s):

C51, B7, B8 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8170L-006 Obj 7 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_...:N..:.:/.!-A:...-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41__55.43_5_Comments: Wednesday, March 10,201010:23:53 AM X 141 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 81.S 015 AA2.02 004/015 AA2.02/2.8/3.0/l/l/C/AiSRO/N/N/RFI Given the following conditions:

-Unit 1 is at 50%power following a refueling outage.-47012-0601, 11 RCP Oil Reservoir HI/La Lvi, is in alarm.-11 RCP Upper Thrust Bearing temperature on recorder 1TR-2001 is LIT.-11 RCP Upper Thrust Bearing temperature is currently reading 180°F and slowly rising.-11 RCP seal injection flow is 6 gpm.-11 RCP NO.1 sealleakoff is 1.2 gpm.What action is required?A.Perform an emergency containment entry to add oil to 11 RCP per F2, Radiation Safety.Initiate a controlled shutdown per 1 C1.4, Unit 1 Power Operation.

When the reactor is shutdown, stop 11 RCP and close the associated spray valve.C.Lower Component Cooling system temperature to minimum per 1C14, Component Cooling System-Unit 1.D.Trip Unit 1 Reactor and enter 1 E-O, Reactor Trip or Safety Injection.

When the reactor trip is verified, stop 11 RCP and close associated spray valve.Justification:

A.Incorrect.

Plausible as oil can be added on line but actual leak location has not been identified.

B.Correct.Per C47012-0601.

C.Incorrect.

Plausible as lower CC temperatures would aid in RCP cooling, however this is not procedurally directed.D.Incorrect.

Plausible as action is required if bearing temps reach 200°F.Wednesday, March 10,201010:23:53 AM 142 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Abnormalities in RCP air vent flow paths and/or oil cooling system Technical Reference(s):

C47012-0601, B3 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8170L-002 Obj 7,6 Question Source: Bank#_Modified Bank#---New X Question History: Last NRC Exam_-=Nc..:.:/"-A-=--

_QuestionCognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content 55.41__55.43 5 Comments: Wednesday, March 10, 2010 10:23:53 AM 143 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 82.S 024 2.4.4 003/024 2.4.4/4.5/4.7/1/2/C/A/SRO/N/NIRFI Given the following conditions:

-Unit 1 Instrument Air Header has depressurized due to a large air leak.-The Reactor was manually tripped.-ONLY ONE Charging Pump is available.

-11 and 12 RCP seal flows are 8 gpm.-Control Rods G 11 and H8 are stuck at 100 steps.-Per 1 ES-0.1, Reactor Trip Recovery, 800 gallons of boric acid is directed to be added to the RCS for the stuck rods.What procedure will the SS direct to be used to add the required amount of boric acid?A.C12.5, Boron Concentration Control.B.C12.6, Boric Acid Transfer Pump and Storage Tank.C't'C12.5 AOP1, Emergency Boration of the Reactor Coolant System.D.1 FR-S.1, Response to Nuclear Power Generation/ATWS.

Justification:

A.Incorrect.

Plausible as this would be an appropriate procedure to use, however without instrument air this is not possible..B.Incorrect.

Plausible as C12.6 contains actions to align the Boric Acid Transfer Pump to the 121 BAST, if the failure is assumed to be limited to the BAST pump feed lines.C.Correct.Without IA the control valves that feed the blender will not function rendering the normal boration path unavailable.

Emergency boration will still function.D.Incorrect.

Plausible as 1 FR-S.1 does contain actions to borate and emergency borate, however the entry conditions for 1 FR-S.1 are not met.Wednesday, March 10, 2010 10:23:53 AM 144 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

Technical Reference(s):

C12.5AOP1, 1ES-0.1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8172L-001a Obj 3 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_.....:Nc.:;/"'-A.:.....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 55.41 10 55.43 5 Comments: Wednesday, March 10, 2010 10:23:53 AM 145 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM 83.S 051 AA2.02 004/051 AA2.02/3.9/4.l/l/2/C/A/SRO/N/N/RFI Given the following conditions:

-Unit 1 is at 100%power.-'A'Condenser Vaccum is 27.9" Hg and stable.-'B'Condenser Vacuum is 25.9" Hg and stable.-C47008-01 08, 1A11 B Condenser Vacuum HI is entered.The Shift Supervisor will direct the crew to...A.reduce load to<350 MWe per 1C1.4, Rapid Power Reduction Unit 1.place the standby air ejector in service using C26, Air Removal System.C.manually trip the reactor and enter 1 E-O, Reactor Trip or Safety Injection.

D.place the hogger jet air ejectors in service using C26, Air Removal System.Justification:

A.Incorrect.

Plausible as this action is directed for a loss of circ pump in C47008-0108.

B.Correct.C47008-0108 step 3 directs placing the standby air ejector in service per C26 C.Incorrect.

Plausible if examinee is considers the alarming setpoint of 2.0" Hg.1P as requiring a reactor trip, however a reactor trip is not required until 2.5'".1P D.Incorrect.

Plausible as are high capacity air ejectors, but they are not effective at removing air after 20" Hg.Wednesday.

March 10,201010:23:53 AM 146 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip Technical Reference(s):

C47 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-251 AU.08 Obj 4 Question Source: Bank#_Modified Bank#_New X 5 Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41__55.43 Comments: Wednesday, March 10,201010:23:53 AM 147 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 84.S 056 2.1.8 001/056 2.1.8/3.4/4.

1/1/1/C/A/SROININIRFI Given the following conditions:-A Loss of Offsite Power has occurred.-A Large Break LOCA is occurring on Unit 2.-47024-0703, 01 Emergency Generator Locked Out, is LIT.-02 is out of service.What action will the Unit 1 Shift Supervisor direct to the outplant operators FIRST?A.Transfer 480V MCCs to Unit 2 supplies.B:-" Locallyclosevalves to isolate RCP seals.C.Reset 01 shutdown relay THEN 86 Lockout.D.Dump steam using the S/G PORVS to cool down the RCS.Justification:

A.Incorrect.

Plausible as this action will be directed, but only if other attempts to restore power are unsuccessful.

B.Correct.This is the first outplant action that will be directed as it will protect the seals.C.Incorrect.

Plausible as this action is directed in the procedure at a later time, but is not the first outplant action that is required.D.Incorrect.

Plausible as this action will be directed, but only if other attempts to restore power are unsuccessful.

Wednesday, March 10,201010:23:53 AM 148 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to coordinate personnel activities outside the control room.Technical Reference(s):

1 ECA-O.O Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 Att.47 Obj 4 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43__Comments: 401.35-Certain"newer" KlAs have a 10 CFR 55 reference given in parenthesis to show a tie between the CFR and NUREG-1122(3).

We were told that questions did not meet the criteria of SRO only (those 25 questions only on the SRO written)if the KIA reference included both 55.41 and 55.43.It is our understanding that questions need be written at SRO knowledge level in these situations.

We do not think that this dual CFR reference should be interpreted to eliminate the KIA from being selected for an SRO question.Thepolicyregarding the 25 SRO-only questions on the written examination is stated in Section D.2.d of ES-401.The fact that a KIA is linked to both 55.41 and 55.43 does not mean that the KIA cannot be used to develop an SRO-only question.Questions related to 55.41 topics may be appropriate SRO-Ievel questions if they evaluate knowledge and abilities at a level that is unique to the SRO job position as determined by the facility licensee's learning objectives.

Wednesday, March 10,201010:23:54 AM 149 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 85.S 057 2.2.25 00l/057 2.2.25/3.2/4.2/1/l/C/NSRO/N/N/RFI Given the following conditions:

-Unit 1 is at 100%power and stable.-Instrument Bus 112 lost power due to a fire in 12 Inverter.-12 Inverter is electrically isolated.-Instrument Bus 112 was manually repowered from Panel 117.Per Technical Specifications, what is the operability status of INSTRUMENT BUS 112 and why?A.Operable, Panel 117 is a Technical Specification equivalent for anyone inverter.Operable, as long as the Instrument Bus voltage is maintained in specifications.

C.Inoperable, the Instrument Bus must be supplied from the inverter.D.Inoperable, Panel 117 is not a regulated supply.Justification:

A.Incorrect.

Plausible as Panel 117 is the backup power supply, but this is not relevant to the operability of the Instrument AC Bus.B.Correct.Per T.S.3.8.9 Basis the only requirement for an Instrument Bus to be operable is that it be maintained at the required voltage.C.Incorrect.

Plausible as inverters have their own tech spec requiring they be operable, but this is not relevant to the question of Instrument Bus operability.

D.Incorrect.

Plausible as the ability to supply a regulated AC supply is a determining factor for inverter operability, but is NOT significant to Instrument Bus operability.

Wednesday, March 10,201010:23:54 AM 150 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.Technical Reference(s):

T.S.3.8.9 Basis Proposed references to be provided to applicants during examination:

None Learning Objective:

P8171 L-007 Obj 4 Question Source: Bank#_Modified Bank#_New X Question History: LastNRCExam_-:Nc..::/c:...A"'--

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41-.1.L 55.43_2_Comments: Wednesday, March 10,201010:23:54 AM X 151 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 86.S 062 A2.16 001/062 A2.16/2.5/2.9/2/1/C/A/SROfNfNIRFI Given the following conditions:

-Unit 1 is at 100%power.-Voltage on 4.16KV Safeguards Bus 16 is 3955 volts.After__seconds, D2 Diesel Generator will auto start and load shedding will be initiated on 4.16KV Safeguards Bus 16.AFTER grid voltage recovers, the Shift Supervisor will direct performance of_______to respond to this event.A.8 1 C20.5, Unit1-4.16KV System B:'60 1 C20.5, Unit1-4.16KV System C.8 1C20.5 AOP2, Reenergizing 4.16KV Bus 16 D.60 1C20.5 AOP2, Reenergizing 4.16KV Bus 16 Justification:

A.Incorrect.

Plausible as this is the appropriate time for a loss of voltage and this is the correct procedure, however the condition given represents a degraded voltage.B.Correct.C.Incorrect.

Plausible as this is the appropriate time for a loss of voltage and this is the correct procedure if voltage were not restored, however the condition given represents a degraded voltage.D.Incorrect.

plausible as this is the appropriate time for load shedding to commence, but the bus will be re-energized making this procedure the wrong choice.Sixty (60)seconds after the DV signal is initiated and maintained, the DG will be started.When up to speed and voltage the offsite sources will be tripped.This will cause a load rejection and a dead bus signal which will allow the DG breaker to close.When the DG breaker closes, load restoration will occur.4.16KV safeguards buses should be maintained between 4000 VAC and 4400 VAC for normal operations (this corresponds to 96.2%to 105.8%of 4160 VA C).Note that the safeguards bus restoration scheme degraded voltage allowable value (T.S.3.3.4.3.b SR)is=3944 Vand=4002 V with a degraded voltage time delay of 8+/-0.5 seconds.Wednesday, March 10,201010:23:54 AM 152 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to (a)predict the impacts of the following malfunctions or operations on the ac distribution system;and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Degraded system voltages Technical Reference(s):

B20.5, 1C20.5, C47024-0304 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8186L-008 Obj 5 Question Source: Bank#_Modified Bank#_

__Question History: Last NRC Exam_--,N...:.:/..:...A.:-.

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments: Wednesday, March 10,201010:23:54 AM x 153 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 87.S 067 2.2.40 003/067 2.2.40/3.4/4.7/1/2/M1SRO/N/N/RFI Given the following conditions:

-Unit 1 is at 100%power.-12 Component Cooling pump is OOS for maintenance as of yesterday at noon.-A fire occurs in the 11 Component Cooling pump.To meet applicable LCO action statements, The Shift Supervisor will direct...A.restoration of ONE Component Cooling train to operable within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.B.restoration of ONE Component Cooling train to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.C.restoration of BOTH Component Cooling trains within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.entry into T.S.3.0.3 and be in Mode 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.Justification:

A.Incorrect.

Plausible as condition B requires this but only if actions of Condition A can not be met.B.Incorrect.

Plausible as the LCO was already entered when 12 Component Cooling pump was declared inoperable thereforethethe time allowed is no longer 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.C.Incorrect.

Plausible if it is assumed condition A can be entered multiple times.D.Correct.LCO 3.0.3 is correct action due to no LCO existing for both trains of Component Cooling being out of service.KIA Statement:

Ability to apply Technical Specifications for a system.Technical Reference(s):

T.S.3.0.3 and 3.7.7 Proposed references to be provided to applicants during examination:

T.S.3.7.7 Learning Objective:

P8172L-002 Obj 10 Question Source: Bank#_Modified Bank#_New

__Question History: Last NRC Exam_--'N...:.:/..:....A:....-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41--,-,1 0:<..-_55.43---:2=---_

Comments: Wednesday, March 10,201010:23:54 AM 154 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 88.S 069 AA2.02 003/069 AA2.02/3.9/4.4/1/2/C/AiSROININIRFI Given the following conditions:

-Unit 1 is at 100%power.-A large break LOCA occurs.-Both Containment Vacuum Breakers AND their associated check valves remain OPEN.-Containment Isolation is MANUALLY initiated from the control room.A(n)is required to be declared.Successful restoration of Containment Integrity will be verified A.Site Area Emergency by Containment pressure stabilizingSite Area Emergency by Containment Isolation Status lights illuminating C.Alert by Containment pressure stabilizing D.Alert by Containment Isolation Status lights illuminating Justification:

A.Incorrect.

Plausible as two barriers are lost so a site Area is appropriate however there are many factors affecting containment pressure so it is not an accurate predictor of valve position.B.Correct.A Site Area emergency exists as there is a loss of RCS integrity and Containment Integrity.

C.Incorrect.

Plausible if only the LOCA is considered and the containment path is assumed, incorrectly, to be an indirect path.There are many factors affecting containment pressure so it is not an accurate predictor of valve position.D.Incorrect.

Plausible if only the LOCA is considered and the containment path is assumed, incorrectly, to be an indirect path and the correct verification method is listed.Wednesday, March 10, 2010 10:23:54 AM 155 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine and interpret the following as they apply to the Loss of Containment Integrity:

Verification of automatic and manual means of restoring integrity Technical Reference(s):

F3-2, 1 E-O, F3-2.1 Proposed references to be provided to applicants during examination:

F3-2, EAL Charts.Learning Objective:

Question Source: Bank#_Modified Bank#---New---'X'-'--

__Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41__55.43 5 Comments: Other KIA: Wednesday, March 10,201010:23:54 AM x 156 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 89.S 034 A2.01 002/034 A2.0l/3.6/4.4/2/2/M/SRO/N/N/RFI Given the following conditions:

-Unit 1 is in Mode 6.-As a fuel assembly was being lifted from the upender to place in the core the gripper opened and dropped the assembly approximately 1 foot.-Gas bubbles are coming to the surface over the fuel.-Containment Atmosphere Monitor, 1 R11, readings are slowly increasing.

Per 05.2 AOP1, Damaged Fuel Assembly, and C1.6 AOP1, Containment Evacuation, the Fuel Handling SRO will notify the Control Room of the damaged fuel assembly and...A.initiate containment closure.sound the containment evacuation alarm.C.notify Nuclear Engineering and Radiation Protection.

D.initiate accountability logging for all personnel in containment.

Justification:

A.Incorrect.

Plausible as containment isolation will be necessary, but this will be performed by the control room and is not an immediate action.B.Correct.1C1.6 AOP1 and 05.2 AOP1 both call for immediate notification of the control room and sounding of the evacuation alarm.C.Incorrect.

Plausible as this action is required, but is performed by the Control Room and is not an immediate action.O.Incorrect.

Plausible as accountability logging will be performed as part of the evacuation, but will be performed by security and is not an immediate action.Wednesday, March 10, 2010 10:23:54 AM 157 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM KIA Statement:

Ability to (a)predict the impacts of the following malfunctions or operations on the Fuel Handling System;and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Dropped fuel element Technical Reference(s):

C1.6 AOP1, 05.2 AOP1 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8182L-003 Obj 3c Question Source: Bank#__Modified Bank#_New X Question History: Last NRC Exam_--=N...:.:/..:...A.:.....-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41__55.43 7 Comments: Wednesday, March 10,201010:23:54 AM 158 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 90.S 0412.4.18001/041 2.4.18/3.3/4.0/2/2/M1SRO/N/N/RFI Given the following conditions:-A Steam Generator Tube Rupture has occurred on Unit 1.-1 E-3, Steam Generator Tube Rupture, Step 7, Initiate RCS Cooldown, is being performed.

What steam release path will the SS direct to cooldown the RCS and why?A'I Condenser Steam Dumps from the intact steam generator, because this path will minimize radiological release.B.Condenser Steam Dumps from the ruptured steam generator, because this path will prevent pressurizing the steam generator to RCS pressure.C.The S/G PORV on the intact steam generator, because this path will ensure adequate capacity to cooldown the RCS.D.The S/G PORV on the ruptured steam generator, because this path will prevent radiological contamination of the Main Steam system.Justification:

A.Correct.Releasing steam from the intact steam generator is the preferred release path in this casualty.B.Incorrect.

Plausible as steam will be released from the ruptured steam generator by the PORV as needed to prevent the overpressurization of the steam generator, but this is not the cooldown method for the RCS.C.Incorrect.

Plausible as the intact steam generator is the appropriate choice for the cooldown and if capacity of the steam dumps is not recognized to be adequate.D.Incorrect.

Plausible as radiological concerns are appropriate and the ruptured steam generator does maintain pressure on the PORV, but this is not the appropriate method of cooling the RCS.Wednesday, March 10,201010:23:54 AM 159 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of the specific bases for EOPs.Technical Reference(s):

1 E-3 Step 7 Bases Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 Atl.43 Obj 3 Question Source: Bank#_Modified Bank#_New X (Question History: Last NRC Exam_....:N...,:,/c:...A.:......

_QuestionCognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41_55.43_4-=--_Comments: Wednesday, March 10,201010:23:54 AM X 160

'-2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 91.S 077 AA2.09 002/077 AA2.09/3.9/4.3/l/I1C/A/SROfNfNIFINAL Given the following conditions:

-Unit 1 is at 100%power.-BKR 15-7, BUS 15 SOURCE FROM BUS CT11, is removed from its cubicle.-A grid disturbance causes BKR 15-3, BUS 15 Source from 1 RY AUX XFMR to trip.-01 Emergency Diesel Generator starts automatically.

-BKR 15-2, BUS 15 SOURCE FROM 01 DSL GEN, does NOT automatically close.-BKR 15-2 is closed from the Control Room and Bus 15 is supplied from 01.What is the operability status of D1?A'!Inoperable BUT available.

B.Inoperable AND unavailable.

C.Operable ONLY while BKR 15-2 remains closed.D.Operable AND available.

Justification:

A.Correct.B.Incorrect.

Plausible if the breaker working makes the diesel available.

C.Incorrect.

Plausible if the diesel carrying the bus is incorrectly assumed to make it operable since it's ability to auto load isn't relevant.D.Incorrect.

Plausible as the diesel is carrying the bus and if it's incorrectly assumed acceptable for the automatic function to be performed manually as it is for some other systems (i.e.PORV's)Wednesday, March 10,201010:23:54 AM 161 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances:

Operational status of emergency diesel generators Technical Reference(s):

T.S.Basis 3.8.1 page 4,5 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8171 L-009 Obj 3 Question Source: Bank#--=-__Modified Bank#_New X Question History: Last NRC Exam_....:N...:.:/..:...A.:.....-

_Question Cognitive Level: MemoryorFundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41-.:5=--_55.43--:2=-_Comments: Wednesday, March 10, 2010 10:23:54 AM X 162 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 92.S 103 A2.01 0021103 A2.01/2.0*/2.6*/2/I/C/A/SROININIRFI Given the following conditions:

-Unit 1 is in Mode 5.-Containment has been pressurized to 46 psig per SP 1071.5, Integrated Leak Rate Test Final Preparations and Test Procedure.

-RCS Temperature is 180°F.-lAW SP 1071.5, RCS Temperature should be held constant (+/-1 OF)for the duration of the test.-1 HC-626A, 11/12 RHR HX Bypass Flow, malfunctions causingCV-31237,RHR HX BYPASS, tofullyOPEN.

As a result, Containment Pressure will and the Shift Supervisor is required to direct entry into_A.raise 1C15 AOP1, RHR Flow Restorationraise 1C15 AOP3, RHR Operation Without Control Room Instrumention or Flow Control C.lower 1C15 AOP1, RHR Flow Restoration D.lower 1C15 AOP3, RHR Operation Without Control Room Instrumention or Flow Control Justification:

A.Incorrect.

Plausible as this is the appropriate pressure response, but RHR Flow restoration does not address valve failures.B.Correct.C.Incorrect.

Plausible as this is the appropriate procedure response and if effects of the bypass valve failing open are not understood.

D.Incorrect.

Plausible if effects of the bypass valve failing open are not understood and if problem is assumed to be restoring pressure.Wednesday, March 10,201010:23:55 AM 163 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to (a)predict the impacts of the following malfunctions or operations on the Containment system;and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

Integrated Leak Rate Test Technical Reference(s):

B15-04 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-003 Obj 4 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments: Wednesday, March 10,201010:23:55 AM X 164 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 93.S 2.1.14 OOl/2.1.14/2.5/3.31111/M/SROlNfBIRFI Per SWI 0-28, Notification of Operations Manager and NRC Resident Inspector, which of the following will REQUIRE notification of the DUTY STATION MANAGER?A'!The crew enters 2C4 AOP1, Reactor Coolant Leak, and isolates the leak.B.An Electrician strains a calf muscle while working on plant equipment.

He later goes home early to rest.C.A planned maintenance activity on the 21 SI Pump begins 45 minutes late.D.AUnit2 operator who has the duty on Tuesday days calls in sick at 0200 on Tuesday morning.Justification:

A.Correct.Entry into 2C4 AOP1 requires DSM notification.

B.Incorrect.

Plausible as injuries with offsite ambulance transport do require notification, however minor injuries do not require notification of the DSM.C.Incorrect.

Plausible as this is an LCO entry, however planned LCO entries even with a slight delay do not require DSM notification.

D.Incorrect.

Plausible as conditions where immediate staffing is required to support the operating crew requires notification, however not this situation.

Wednesday, March 10,201010:23:55 AM 165 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of system status criteria which require notification of plant personnel Technical Reference(s):

SWI 0-28, Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-238 Obj A Question Source: Bank#P9150L-00321 Modified Bank#_New---Question History: Last NRC Exam_-'N'-"/c:..A.:-

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41--,-,1 0"---_55.43__Comments:.401.35-Certain"newer" KlAs have a 10 CFR 55 reference given in parenthesis to show a tie between the CFR and NUREG-1122(3).

We were told that questions did not meet the criteria of SRO only (those 25 questions only on the SRO written)if the KIA reference included both 55.41 and 55.43.It is our understanding that questions need be written at SRO knowledge level in these situations.

We do not think that this dual CFR reference should be interpreted to eliminate the KIA from being selected for an SRO question.The policy regarding the 25 SRO-only questions on the written examination is stated in Section D.2.d of ES-401.The fact that a KIA is linked to both 55.41 and 55.43 does not mean that the KIA cannot be used to develop an SRO-only question.Questions related to 55.41 topics may be appropriate SRO-Ievel questions if they evaluate knowledge and abilities at a level that is unique to the SRO job position as determined by the facility licensee's learning objectives.

Wednesday, March 10,201010:23:55 AM 166 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 94.S 2.1.5 003/2.1.5/2.9*/3.9/3/M/SROIN/M/RFI Given the following conditions:

-Both Units are at 100%power-At 0100 the Unit 1 Shift Supervisor receives a phone call from the Unit 1 APEO informing him he must leave the site for personal reasons.Which of the following is allowed per SWI 0-2, Shift Organization, Operation&Turnover?A.The position may remain vacant until the day shift operator arrives at 0600.B!'" The position may be vacant for up to two hours if immediate action is taken to fill it.C.The position may be filled by an extra crew member who is a qualified as a Plant Attendant.

D.The position may be vacant for up to one hour to determine if the operator can return before action is taken to fill it.Justification:

A.Incorrect.

Plausible if it assumed since a replacement is scheduled no action is required SWI 0-2.B.Correct.Per SWI 0-2, the APEO position must be filled or action taken to ensure the position is not vacant for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.C.Incorrect.

Plausible as plant attendants and APEO's perform similar functions, but the APEO position is not interchangeable.

D.Incorrect.

Plausible if it assumed there is a grace period to determine if action is required.KIA Statement:

Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.Technical Reference(s):

SWI 0-2 pg 5 Section 6.1.8, T.S.5.2.2 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140L-214 Obj SWI 0-2 Question Source: Bank#_Modified Bank#_-,-P....",8:...,:.1....:..;40=L::....;-2=-1.:....;4:....,:0,,-,1c....:.1

__New_Question History: Last NRC Exam_-=N:...:.:/c:....A-=-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 2 Comments: Wednesday.

March 10, 2010 10:23:55 AM x 167 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 95.S 2.2.17 003/2.2.17/2.6/3.8/3/C/NSRO/NIM/RFI Given the following conditions:

-Unit 2is at 100%power.-It is Sunday afternoon.

-21 RHR pump locks out during a surveillance run.-The breaker check shows a'51A'relay tripped.-LCO 3.5.2, ECCS-Operating, Condition A is entered.What priority should this work be assigned AND what actions regarding callout of personnel should be taken?A'!Designate this work as Priority 1 Call the Duty Station Manager to initiate work planning and scheduling immediately.

B.Designate this work as Priority 2 Inform Site Management that this work must be planned and work begun on Monday.C.Designate this work as Priority 3.Inform Site Management that this work must be planned and work begun on Monday.D.Designate this work as Priority 4.Call the Duty Station Manager to initiate work planning and scheduling immediately.

Justification:

A.Correct.LCOs less than 14 days require immediate attention per fleet procedure FP-WM-WOI-01.

B.Incorrect.

Plausible if it is assumed monday morning will be soon enough as it's sunday afternoon.

C.Incorrect.

Plausible if priority levels are confused and higher number is assumed to mean higher priority.D.Incorrect.

Plausible as the actions shown are correct and if the priority numbers are confused and higher number is assumed to mean higher priority.Wednesday, March 10, 2010 10:23:55 AM 168 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM KIA Statement:

Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.Technical Reference(s):

FP-WM-WOI-01 Proposed references to be provided to applicants during examination:

None Learning Objective:

P9150L-005 Obj 4.Question Source: Bank#--Modified Bank#P9150L-005008 New_Question History: Last NRC Exam_....:N...;;;/..:...A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:

55.43__Comments: Wednesday, March 10, 2010 10:23:55 AM_x_169 2010 PRAIRIE ISLAND IL T NRC WRITIEN EXAM 96.S 2.2.35 002/2.2.35/3.6/4.5/3/M/SROfNfN/RFI Given the following conditions:

-RCS temperature is 250°F and stable.-Both RCS Loops are available for operation.

-11 RHR pump is in service.What are Technical Specifications requirements for SI pumps in this condition and why?A.ONLY ONE SI pump may be capable of injecting into the core to prevent exceeding maximum cool down rate of the RCS.B.BOTH SI pumps must be capable of injecting into the core to ensure adequate heat removal in a Design Basis Accident.C.NO SI pumps may be capable of injecting into the core to prevent damage to SI pump due to runout.ONLY ONE SI pump may be capable of injecting into the core to prevent overpressurization of the RCS.Justification:

A.Incorrect.

Only one SI pump is allowed between OPPS enable temp (310°F)and SI pump disable temp (218°F)but not due to RCS overcooling.

B.Incorrect.

Plausible if tech spec mode of operation is not correctly identified and at power tech spec requirements are used.C.Incorrect.

Plausible as making neither SI pump capable of injection would satisfy one T.S.requirement at the given conditions, but would violate another applicable T.S.D.Correct.Wednesday, March 10,201010:23:55 AM 170 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Ability to determine Technical Specification Mode of Operation.

Technical Reference(s):

T.S 3.4.12 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8180L-004 Obj 10 Question Source: Bank#_Modified Bank#_New X Question History: Last NRC Exam_--=N....:.:/..:...A"--

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43-=2=-_Comments: Wednesday, March 10,201010:23:55 AM 171 2010 PRAIRIE ISLAND ILT NRC WRITTEN EXAM 97.S 2.3.4 005/2.3.4/2.5/3.1/3/C/NSRO/N/N/FINAL Given the following conditions:-A LOCA outside containment occurred on Unit 2.-A General Emergency has been declared.-An employee is injured and cannot leave the auxiliary building without assistance.

-Initial dose estimates are 77 R/hour gamma in the vicinity of the injured worker.-The rescue time fora2 person team is estimated to be 20 minutes.The is the lowest level of approval acceptable for THIS rescue mission, and it will be performed using personnel who_A.Radiological Emergency Coordinator have volunteered EXCLUSIVELYEmergency Director have volunteered EXCLUSIVELY C.Radiological Emergency Coordinator are assigned regardless of volunteer status D.Emergency Director are assigned regardless of volunteer status Justification:

A.Incorrect.

Plausible as the REC is responsible for briefing the rescuers and control their dose, but is not the appropriate authorizer.

B.Correct.As this rescue will result in an over exposure the ED must authorize it.C.Incorrect.

Plausible as REC is a cognizant body and if the exposure is calculated incorrectly or the limit is not known.D.Incorrect.

Plausible as the ED is the appropriate authorizer and if the exposure is calculated incorrectly or the limit is not known.Wednesday, March 10,201010:23:55 AM 172 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Knowledge of radiation exposure limits under normal or emergency conditions.

Technical Reference(s):

F3-12, F3-11 Proposed references to be provided to applicants during examination:

None Learning Objective:

P9130L-003 Obj 6 Question Source: Bank#----'1'-_Modified Bank#_New---'X-'--__(Question History: Last NRC Exam_....:N...:.:/..:...A.:....-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 12 55.43_4_Comments: Wednesday, March 10, 2010 10:23:55 AM 173 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 98.S 2.4.11 003/2.4.11/4.0/4.2/3/M1SRO/N/B/RFI Given the following conditions:

-Unit 1 is at 100%power and stable.-47020-0203, 11 CC Surge Tank HI/LO LVL, is LIT.-1 R-39, CC System Liquid Monitor, is in HI alarm.-47015-0108, 11 RCP Thermal Barrier CC Water HI Flow, is LIT.The SS will direct entry into...A.1 E-O, Reator Trip or Safety Injection.

B.1 C1.4 AOP1, Rapid Power Reduction-Unit 1.C.1C14 AOP1, Loss of Component Cooling.D\" 1C14 AOP2, Leakage Into the Component Cooling System.Justification:

A.Incorrect.

Plausible if failure is recognized as thermal barrier leakage and it is assumed this condition requires the RCP to be secured.B.Incorrect.

Plausible if it is assumed this condition will eventually require the securing of the RCP and rapid downpower is preferrable to a full trip.C.Incorrect.

Plausible as this does represent leakage in the CC system, but this AOP is to address loss of CC and is not applicable to these conditions.

D.Correct.KIA Statement:

Knowledge of abnormal condition procedures.

Technical Reference(s):

C47020-0203 Proposed references to be provided to applicants during examination:

None Learning Objective:

P8140S-200 AU.27 Obj 4c Question Source: Bank#P8172L-002037 Modified Bank#---New---Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis10 CFR Part 55 Content: 55.41--1.L 55.43 5 Comments: Wednesday, March 10, 2010 10:23:55 AM 174 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 99.S 2.4.30 00l/2.4.30/2.7/4.l/3/C/A/SRO/N/B/RFI Given the following conditions:

-Unit 1 is operating at 100%power and stable.-PCV-430, PRZR PORV, inadvertently opens.-Plantstabilizationactions have been completed.

-The PORV is declared out of service.Which of the following describes the reporting, if any, that must be made to the NRC?(Assume the plant remains at 100%power.)A.None required B.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> non-emergency report via the ENS.C.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> non-emergency report via the ENS.24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report to the NRC Resident Inspector.

Justification:

A.Incorrect.

Plausible if reporting is assumed unecessary due to the leak being quickly isolated.B.Incorrect.

Plausible if reporting requirements are not understood.

C.Incorrect.

Plausible if reporting requirements are not understood.

D.Correct.PI has a commitment with the NRC to report any failures of PRZR PORV's or Safeties within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.KIA Statement:

Knowledge of events related to system operations/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.Technical Reference(s):

5AWI 3.6.0 Proposed references to be provided to applicants during examination:

PINGP 666 Learning Objective:

P9150L-011 Obj 3 Question Source: Bank#P7410L-032 001 Modified Bank#_New_Question History: Last NRC Exam_....;NC-:""'-A.:..-

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X10 CFR Part 55 Content: 5 (Comments: Wednesday, March 10,201010:23:55 AM 55.41__55.43 175 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM 100.SE 12 2.4.41 001/040 2.4.4l/2.9/4.6/1/1/C/A/SRO/N/N/RFI Given the following conditions:-Unit1 was at 100%power.The following THEN occurs:-At 0300:-11 Steam Generator faults to containment.-A Reactor Trip and Safety Injection occurs.-A Loss of Offsite Power occurs.-01 and 02 start and supply Bus 15 and Bus 16.-C47019-01 02, 12 Containment Spray Pump Locked Out, is lit.-At 0305:-Bus 15 locks out.-Containment pressure is 29 psig and rising.-At 0310:-Offsite Power is restored.A(n)should be declared within 15 minutes of_A'I NUE the Bus 15 lock out B.Alert the Bus 15 lock out C.NUE losing Offsite Power D.Alert losing Offsite Power.Justification:

A.Correct.FU1 Potential loss of containment barrier item 2 containment pressure,>23 psig with<1 full train of depressurization equipment operating.

B.Incorrect.

Plausible as this would be the required escalation

'and time if the time requirement of the offsite power NUE is not recognized.

C.Incorrect.

Plausible as this declaration would be necessary at this time if offsite power were not restored within 15 minutes.D.Incorrect.

Plausible as declarations can be combined if the higher order declaration is made within the time frame to declare the lower order declaration however the higher declaration is not required by the given conditions.

Wednesday, March 10, 2010 10:23:56 AM 176 2010 PRAIRIE ISLAND IL T NRC WRITTEN EXAM KIA Statement:

Steam Break.Knowledge of the emergency action level thresholds and classifications.

Technical Reference(s):

B15, PINGP 1576, FSAR, TS 3.5.4, F3-2 Proposed references to be provided to applicants during examination:

F3-2, EAL Charts.Learning Objective:

P741 OL-034 Obj 10 Question Source: Bank#_Modified Bank#---New---,X,-,-__Question History: Last NRC Exam

_Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43_5_Comments: You have completed the test!Wednesday, March 10,201010:23:56 AM 177