Text

Final - RO & SRO Written Examination with Answer Key (401-5 Format) (Folder 3)
	ML070610491
Person / Time
Site:	Peach Bottom
Issue date:	01/29/2007
From:	Vanwyen T; Exelon Generation Co
To:	Todd Fish; Operations Branch I
	Sykes, Marvin D.
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ML060800089	List: IR 05000277/2007301; ML070310224; ML070380284; ML070380292; ML070380304; ML070380334; ML070380337; ML070610478; ML070610491; ML070610496; ML070610499; ML070610509; ML070610511; ML070790539; ML071010332; ML071020269;
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Question 1 Details Question Type: Multiple Choice Topic: N-ILT-1540-3-011 Unit 2 is operating at 95% power when a recirculation flow reduction event results System ID: 1268 User ID: N-ILT-1540-3-011 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295001.AA2.02 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.1 / SRO 3.2 Cognitive-Level: Memory

References:

OT-I 12 Justification:

A. Incorrect - RBM not referenced as a nuclear monitoring instrument for THI.

B. Correct - Core Thermal Hydraulic Instability (THI) may be occurring if any of the following conditions exist: *Steadily increasing confirmation counts on OPRM display with few to no resets.

Any APRM flux noise signal grows by 2 or more times its initial level,

APRM flux oscillations rise greater than or equal to 10% (peak to peak).

C. Incorrect - No reference to period indication as a nuclear monitoring instrument for THI.

D. Incorrect - Steadily increasing Confirmation counts on OPRM display causing repetitive "OPRM Pre-trip Condition" alarms is indication of THI.

NRC EXAM Page: 2 of 144 01131IO7

2 ID:N-ILT-5057-6A-003 Points: 1.00 0 A Station Blackout has occurred.

Personnel will operate equipment to shed DC loads in accordance with SE-11, "Loss of Off-Site Power", Attachment T, "DC Load Shed" in order to:

A. provide sufficient long-term power for Main Control Room annunciators B. ensure sufficient DC load capacity to allow for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months operability of the HPCl system.

C. ensure power to equipment required for adequate core cooling and restoration of AC power.

D. provide continued Main Control Room Emergency Ventilation control power up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the total loss of AC.

Answer: C NRC EXAM Page: 3 of 144 01131107

Question Type: Multiple Choice Topic: N-ILT-5057-6A-003 A Station Blackout has occurred.

In accordance with SE-11, "Loss of Off-Site Powe System ID: 1269 User ID: N-ILT-5057-6A-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295003AA1.04 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.6 / SRO 3.7 Cognitive-Level: Memory

References:

SE-I 1, DBD P-S-OIA, P-T-13"Station Blackout" Justification:

A. Incorrect - Only selected MCR annunciators are left with DC power. The remainder will be shed per SE-11, Attachment T.

B. incorrect - Even if a DC load shed is initiated immediately after the loss of power, then battery life ~ a bey extended beyond 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , but not as long as 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The inaccurate 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months time frame is used as a plausible distracter for any examinee who does not recall 2 or 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months battery limits under station blackout conditions.

C. Correct - Per SE-11 Bases the DC Load Shed on non-essentialloads is to assume enough power for equipment such as ECCS Logic, RClC Logic and Control, Diesel Logic &

Control, SRVs .... which are required for adequate core cooling and circuit breaker control to help restore AC power.

D. Incorrect - The Main Control Room Emergency ventilation control power is AC, not DC.

NRC EXAM Page: 4 of 144 01131IO7

EXAMINATION 007

.-/- Question 3 Details Question Type: Multiple Choice Topic: N-ILT-5057-3C-002 Effect of a charger malfunction on OC battery System ID: 1176 User ID: N-ILT-5057-3C-002 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295004 AK2.02 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.0 / SRO 3.1 Cognitive-Level: High

Reference:

PLOT 5057, Objective 3c; E-26 Justification:

A. Incorrect - charger 280003-2 must be manually placed in service...only one charger can be in service at a time. The question stem states "assuming no operator actions."

B. Incorrect -when the output breaker for charger 2BD003-1 trips, the charger no longer supplies power to the Division II 250 VDC bus. The bus loads would then be supplied by BOTH the 2B and 2D batteries.

C. Incorrect - the battery will fully support all loads for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with no battery charger; the bus will remain energized.

D. Correct - when the output breaker for charger 2BD003-1 trips, the charger no longer supplies power to the Division I1 250 VDC bus. The bus loads would then be supplied by the 2B and 2D batteries. The batteries are designed to supply loads during a DBA for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

NRC EXAM Page: 6 of 144 01/31/07

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Quhtion 4 Details 1 k, Question Type: Multiple Choice Topic: N-ILT-5060F-11-001 Unit 2 is operating at 20% power.

A ground fault on the Grid resulted in the System ID: 1270 User ID: N-ILT-5060F-I1-001 Status: Active Always select on test: No Authorized for practice: No DifficuIty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295005.AA2.05 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 / SRO 3.9 Cognitive-Level: Memory

References:

ARC 210 A-2 Justification:

A. Incorrect - The main turbine will trip on a generator lockout.

B. Incorrect - The reactor will not scram less than 30% reactor power on Turbine Stop Valve or Turbine Control Valve closure C. Correct - The Turbine Stop Valve and Turbine Control Valve closure scrams are bypassed at less than 30% power since high pressure scram is adequate to protect the reactor.

D. Incorrect- The reactor will not scram less than 30% reactor power on Turbine Stop Valve or Turbine Control Valve closure.

NRC EXAM Page: 8 of 144 01/31/07

ANS RO Rev 1 Question5 Details Question Type: Multiple Choice Topic: N-ILT-5006-1A-004 RPV Which of the following describes the initial reactor water level response to a System ID: 1363 User ID: N-lLT-5006-1A-004 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295006 AK3.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 I SRO 3.9 Cognitive-Level: Memory Reference : PLOT 5006 Obj. 1; Fundamentals Justification:

A. Incorrect - RPV level will initially lower as a result of voids collapsing.

B.Correct - RPV level will initially lower as a result of voids collapsing in the core region.

C. Incorrect - RPV level will initially lower as a result of voids collapsing.

D. Incorrect - Water discharged to the SDV comes mainly from the HCUs and is insignificant in volume compared to the level reduction in the RPV post scram.

NRC EXAM Page: 10 of 144 0 1I3 1 io7

EXAMINAT Question 6 Details Question Type: Multiple Choice Topic: N-ILT-1555-1-014Which one of the following is the reason why the reactor is SCRAMMED prior to evac System ID: 1271 User ID: N-ILT-1555-1-014 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295016.AK3.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 4.1 / SRO 4.2 Cognitive-Level: Memory

References:

SE-1 Justification:

A. Incorrect - HPCl is used only in SE-10 at the Alternate Shutdown Panel and not applicable for this condition.

6. Correct - In accordance with SE-1 bases, scramming the unit assures that makeup to the reactor will be based on decay heat which can be adequately handled by the RCIC System.

C. Incorrect - Per SE-1 bases this is the reason for closing the MSIVs, not scramming the reactor.

D. Incorrect - MSlVs are manually closed prior to evacuation and all Group Isolations are expected during SE-1.

NRC EXAM Page: 12 of 144 01/31/07

L" ID:N-ILT-1550-18A-001 Points: 1.00 Unit 3 was operating at 100% power when the following occurred:

0 'A' RBCCW pump tripped due to an overcurrent condition.

0 'B' RBCCW pump started automatically but at a reduced discharge pressure.

0 RBCCW System temperatures are rising steadily.

Per ON-1 13 bases, the reason ON-1 13 "Loss of RBCCW' directs the RWCU pumps tripped and the system isolated is to:

A. isolate a likely primary-to-secondaryleak in the RBCCW heat exchangers.

6. allow more time to diagnose and correct the cause of the RBCCW problem.

C. prevent RWCU pump cavitation due to high reactor water inlet temperature.

D. reduce the required RBCCW System flow rate thereby preventing pump runout.

Answer: B NRC EXAM Page: 13 of 144 01I31IO7

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Question 10 Details Question Type: Multiple Choice Topic: N-ILT-5010-3F-001 *Unit 2 is in MODE 4 twenty-four hours after shutdown, following an extended full System ID: 1322 User ID: N-ILT-5010-3F-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: I.oo Cross

Reference:

295021AK1.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.6 / SRO 3.8 Cognitive-Level: High

References:

ON-125,GP-12 Justification:

A. Incorrect - With the RHR pump tripped there is no longer shutdown cooling flow from the reactor vessel to the RHR heat exchanger.

B. Correct - Decay heat will cause RPV coolant temperature to rise and eventually reach boiling. Reactor pressure will increase above atmospheric pressure (NOTE: Even if examinee assumes RPV head vents are open pressure will stili increase since the head vents are on a 1" line and are designed for removal of non-condensiblesat power or air removal for refueling or hydro test conditions. There is industry OE that confirms that bulk boiling of coolant due to lack of shutdown cooling will result in going greater than 212 F and pressurizing the RPV with the vents open).

C. Incorrect - Reactor pressure will increase above atmospheric.

D. Incorrect - With the RHR pump tripped there is no longer shutdown cooling flow from the reactor vessel to the RHR heat exchanger.

NRC EXAM Page: 20 of 144 01/31/07

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Question 11 Details Question Type: Multiple Choice Topic: N-ILT-1550-27A-001 Unit 2 is shutdown for a refueling outage with the fuel pool gates installed.

System ID: 1274 User ID: N-ILT-1550-27A-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295023.AA.1.02 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.9 / SRO 3.1 Cognitive-Level: High

References:

ARC 20C076 (D-2), ARC 20C075 (B-l),

ON-124, FH-74 Justification:

A. Incorrect - Fuel pool level has decreased and has resulted in the alarm. The level in the skimmer surge tanks are the same. The second pump will not start because the level in the skimmer surge tank has fallen below the low low level pump trip setpoint.

B. Correct - ARC 206076 (D-2) will refer the Equipment Operator to SO 19.3.A-2, Fuel Pool Filling Skimmer Surge Tank via Normal Make-up Line which utilizes the Condensate Transfer System C. Incorrect - The control rod drive pump will inject into the reactor vessel and will not effect the level in the fuel pool due to fuel pool gates being installed.

D. Incorrect - The fuel pool gates are installed and because of this, addition of water to the cavity will have no effect on the fuel pool level.

NRC EXAM Page: 22 of 144 0 1I31107

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, :I2 ID:N-~LT--I~~o-~-oo-I Points: 1.00 0 Unit 2 is operating at 100% power Drywell Pressure unexpectedly rises to 1.2 psig and is trending up.

OT-101, "High Drywell Pressure" has been entered.

The operating crew must IMMEDIATELY:

A. perform GP-3, "Normal Plant Shutdown" B. perform GP-4, "Manual Reactor Scram".

C. scram and enter T-101, "RPV Control" ONLY D. scram and enter T-101 "RPV Control" AND T-102 "Primary Containment Control".

Answer: B Question 12 Details Question Type: Multiple Choice Topic: N-ILT-1540-3-001 Unit 2 is operating at 100% power when Drywell pressure unexpectedly rises to 1.2 System ID: 22 1 User ID: N-ILT-1540-3-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295024 G2.4.49 User Text: A User Number 1: 6286.00 User Number 2: 0.00 Comment: Importance: RO 4.0 / SRO 4.0 Cognitive-Level: Memory

References:

PLOTl540.03, OT-I 01 Justification:

A. Incorrect - Not required unless both seals on a Recirc Pump fail. However, requirement to scram at 1.2 psig still applies.

B. Correct - A GP-4 Manual Scram is required at 1.2 psig in Drywell.

C. Incorrect - T-101 is not required to be entered until drywell pressure reaches 2.0 psig.

D. Incorrect - T-I 01 and T-102 are not required to be entered until drywell pressure reaches 2.0 psig.

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NRC EXAM Page: 23 of 144 07/31/07

13 ID:N-ILT4001A-5G-001 Points: 1.00 0 Unit 3 had been operating for 340 days when a reactor scram occurred.

0 15 minutes after the scram, plant conditions are as follows:

A Group 1 isolation has occurred and has not been reset.

9 Control Rods are at position 02.

RClC tripped on overspeed and cannot be restarted.

HPCI is out of service.

Reactor water level is +15 inches and has remained steady.

Reactor pressure is 1140 psig.

Why is RPV pressure 1140 psig AND, assuming no operator action, what is the status of the Safety Relief Valves (SRVs)?

A. Multiple rods still out, AND SRVs are closed.

B. Decay heat generation, AND SRVs are closed.

C. Decay heat generation, AND SRVs are controlling pressure in self-actuation mode.

D. Multiple rods still out, AND SRVs are controlling pressure in self-actuation mode.

.-/ Answer: C W

NRC EXAM Page: 24 of 144 01131107

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ANS g 0 Rev 1 Question 14 Details Question Type: Multiple Choice Topic: N-ILT-1540-4-011 Unit 3 is operating at full power when a Safety Relief Valve fails full open and ca System ID: 1367 User ID: N-ILT-1540-4-011 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295026EK2.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.9 / SRO 4.0 Cognitive-Level: Memory

References:

OT-114 and bases; T.S 3.6.2.1 Justification:

A. Incorrect - SRV heat input exceeds Torus Cooling capacity whether one or both loops are placed in service.

B. Incorrect - SRV heat input exceeds Torus Cooling capacity whether one or both loops are placed in service.

C. Incorrect - reducing power will only slightly lower pressure and is accomplished to try and shut the SRV.

It does not reduce the heat input of an open SRV.

Heat input is more a function of RPV pressure than power.

D. Correct - the plant must be shutdown and depressurized to prevent the Torus from continuing to heat up.

NRC EXAM Page: 27 of 144 01/31/07

f15 ID:N-ILT-21164A601 Points: 1.00 Per T-116 bases, the reason for entering T-I 16, "RPV Flooding" procedure during a high drywell temperature condition is to establish:

A. Flooding conditions before SRVs fail due to exceeding the SRV cabling design temperature.

B. Flooding conditions before exceeding primary containment design temperature.

C. Adequate core cooling when RPV level cannot be determined due to indicated level errors from reference leg flashing.

D. Adequate core cooling when RPV level cannot be determined due to indicated level errors from variable leg flashing.

Answer: C NRC EXAM Page: 28 of 144 01/31/07

Question 15 Details Question Type: Multiple Choice Topic: N-ILT-2116-4A-001 The bases for entering T - I 16, RPV Flooding procedure during a high drywell tempe System ID: 1276 User ID: N-ILT-2116-4A-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295028 EK3.02 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.5 / SRO 3.8 Cognitive-Level: Memory

References:

T-I 16 Bases Justification:

A. Incorrect - SRV cabling design temperature used to be described in T - I 12 Bases. It is no longer mentioned in any basis document and is no longer an immediate concern.

B. Incorrect - Containment design temperature is not mentioned as a reason for entry into T-I 16 per the bases.

C. Correct - Per T-116 Bases one of the probable causes of erroneous RPV level indications is boiling of water in the reference leg due to elevated DrywelI temperatures.

D. Incorrect - The concern is for reference leg flashing, not variable leg flashing.

NRC EXAM Page: 29 of 144 01131/07

'I6 ID: N-ILT5059K-1A-002 Points: '1.00 Unit 2 is at 30% power with GP-2, "Normal Plant Start-up", in progress.

RPV water level is +24 inches.

Annunciator 224 (E-5) TORUS ROOM FLOOD is lit in the main control room.

A significant water leak is identified in the Torus

The crew enters T-102, "Primary Containment Control", at a Torus level of 14.5' and lowering.

Per T-102 "Primary Containment Control", if Torus level cannot be maintained above 12.5 ' you are required to (1) based on (2) :

A. (1) Manually scram the reactor per GP-4 (2) Torus level indicators in the Main Control Room OR from SPDS B. (1) Perform an Emergency Blowdown per T-I 12 (2) Torus level indicators in the Main Control Room ONLY.

C. (1) Manually scram the reactor per GP-4 (2) Torus level indicators in the Main Control Room ONLY.

D. (1) Perform an Emergency Blowdown per T - I 12 (2) Torus level indicators in the Main Control Room from SPDS.

Answer: C NRC EXAM Page: 30 of 144 01131107

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.4/ 17 ID: N-ILT-2101-1-010 Points: 1.00 The following conditions exist on Unit 2 following a small LOCA:

0 All control rods are fully inserted.

0 RPV Level is -120 inches and lowering at 2 inches per minute.

0 RPV Pressure is 960 psig and steady.

0 Drywell Pressure is 4 psig.

0 Torus Pressure is 3 psig.

0 MSlVs are closed.

0 HPCl and RClC are both unavailable for injection.

Which of the following actions are required?

A. Lineup and start HPSW pumps to inject per T-245.

B. Rapidly depressurize the RPV with BPVs per step T-101 RCIP-12.

C. Lower RPV pressure to inject with Core Spray without exceeding the Technical Specification Cooldown limits.

D. Lower RPV pressure to inject with Condensate without exceeding the Technical Specification Cooldown limits.

Answer: D NRC EXAM Page: 32 of 144 01131IO7

J Question 17 Details Question Type: Multiple Choice Topic: N-ILT-2101-1-010 The following conditions exist on Unit 2 following a small LOCA:

RPV level is System ID: 1279 User ID: N-ILT-2101-1-010 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 4 Point Value: 1.oo Cross

Reference:

295031 EA2.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 4.2 I SRO 4.2 Cognitive-Level: High

Reference:

T-101 and Bases, T-I 12 and Bases, T-102 and Bases.

Justification:

A. Incorrect - Per T-245, "HPSW Injection into the R P V placing the HPSW pumps inservice and the majority of valve manipulations are not completed until RPV pressure is below 400 psig.

B. Incorrect - For the conditions given, the plant is not approaching a limit that requires an Emergency Blowdown (T-112) in T - I 02, T-I 03, T-I 04. RC/P-12, rapidly depressurize with BPVs, is not used. In addition, the MSlVs are closed which eliminates use of BPVs.

C. Incorrect - The Core Spray system will not inject into the RPV until RPV pressure is lower than 330 psig. Lowering pressure to below 330 psig will be a violation of the Tech Spec 100°F/hr cooldown rate.

D. Correct - T-I 01 steps RCIP-16 directs beginning an RPV depressurization maintaining cool down rate below 100" F/hr.

RC/P-16 along with RCIL-3 allows for using Condensate system to restore RPV level.

NRC EXAM Page: 33 of 144 01131107

EXAMINATION Question 18 Details e '*

Question Type: Multiple Choice Topic: N-ILT-2101-6-002 Unit 2 has scrammed, it is determined that seven (7) control rods located randomly System ID: 1323 User ID: N-ILT-2101-6-002 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295037 EK1.07 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.4 / SRO 3.8 Cognitive-Level: High

References:

T-101 Bases Justification:

A. Incorrect - Boron would not have been injected for these reactor/containmentconditions.

B. Correct - The only condition allowing exit from Leg RC/Q Rods is when an ATWS is no longer in progress. Note #24 states that termination of an ATWS requires determination that: (1)

All rods are inserted to or beyond the maximum subcritical banked withdrawal position (MSBWP) of "02". OR (2) With any single rod fully withdrawn past 00, all other rods are fully inserted. (3) The reactor will remain shutdown under all conditions on rod insertion alone regardless of boron concentration (RE calculation}.

C. Incorrect - 4% reactor power is the reference for entry into T-101, "RPV Control". Leg RC/Q rods makes no reference to 5 4% power as an exit requirement.

D. Incorrect - Termination of ATWS Note #24 makes no reference to RHR Shutdown Cooling mode of operation.

NRC EXAM Page: 35 of 144 0 1131IO7

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Which of the following fire fighting systems is designed to mitigate a fire in the Standby Gas Treatment filter trains AND how is it initiated?

A. Cardox, Manually B. Water Curtain, Automatically C. Water Deluge, Manually D. Water Deluge, Automatically Answer: C Question 20 Details Question Type: Multiple Choice Topic: N-ILT-5037-4F-002 Unit 2 and Unit 3 are operating at 100% power. The Main Control Room receives System ID: 1281 User ID: N-ILT-5037-4F-002 Status: Active Always select on test: No L..' Authorized for practice: No Difficulty: 2.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

600000 AA1.08 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.0 / SRO 2.9 Cognitive-Level: Memory

References:

ARC 007 J-6b, PLOT-5009A I

Justification:

A. Incorrect - There is no cardox system associated with the SBGT system.

B. Incorrect - There is no water curtain associated with the SBGT system. The water curtain is for Reactor Building 135' area.

C. Correct - The SBGT filters have a sprinkler deluge system that is manually initiated. Other than MCR alarm and detection, there are not automatic actions for fire suppression.

D. Incorrect- The SBGT filters have a sprinkler/deluge water system that is manually initiated. There is no system automatic fire suppression equipment for SBGT.

NRC EXAM Page: 38 of 144 0 1I31IO7

21 'i .ID: N-ILT-I5404-009 Points: 1.00 Unit 2 is at 85% power when annunciator 210 H-2, REACTOR HI-LO WATER LEVEL alarms The following conditions exist:

RPV level is +31 inches and rising.

Total feed flow is greater than total steam flow.

"A' RFP speed is 4700 rpm and rising.

"6" RFP speed is 4300 rpm and lowering.

"C' RFP speed is 4500 rpm and steady.

Based on the above indications, the -(I)- RFP is operating correctly and the -(2)- RFP should be taken to manual control.

A. ( 1) "A" (2) "C" B. (1) "B" (2) "A"

c. (1)"C (2) "A" D. (1)"A" (2) "B" Answer: B NRC EXAM Page: 39 of 144 01I31IO7

Question 21 Details Question Type: Multiple Choice Topic: N-ILT-1540-4-009 Unit 2 is at 85% power when annunciator 210 H-2, REACTOR HI-LO WATER LEVEL alarms.

System ID: 1283 User ID: N-ILT-1540-4-009 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.00 '

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Reference:

29500862.4.50 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 I SRO 3.3 Cognitive-Level: Memory 1

Referdnces: OT-I 10 Justification:

A. Incorrect - "A' RFP speed is rising. The Operator should take manual control of the "A' RFP due to speed rising contrary to feedwater system control.

B. Correct - If feed flow is > steam flow, RPV level will rise. The RFP master level controller will attempt to lower ALL RFP speeds. Only the "B" RFP speed is operating correctly. The "C" RFP control is not responding (speed is constant). The "A" RFP controller has failed because speed is rising.

C. Incorrect - The "C" RFP speed should be lowering in response to the high RPV water level. However, the "A' RFP is actually rising in speed and has an immediate detrimental effect on rising water level and should be the higher priority for manual control.

D. Incorrect - "A' RFP speed is rising and is not operating properly in response to a high reactor level.

NRC EXAM Page: 40 of 144 01/31/07

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-22 ID: N-ILT-1546-5-004 "Poirib:1.00 Unit 2 was at 100% power when an unidentified leak into the primary containment caused an automatic reactor scram The following conditions are present on Unit 2

All rods are inserted.

RPV level is -5 inches and rising slowly.

RPV pressure is 940 psig and dropping.

House Loads have been transferred.

Based on the above conditions, reactor recirculation pump speed is presently -( 1- due 0

-(2)-.

A. (1) 30%

(2) a scram signal being present with RPV level less than +I 7 inches.

B. (1) 30%

(2) individual reactor feedpump flows less than 20% with RPV level less than

+ I 7 inches.

c. (A)&%

(2) a scram signal being present with RPV level less than + I 7 inches D. (1) 45% I (2) individual reactor feedpump flows less than 20% with RPV level less than

+17 inches.

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Answer: A NRC EXAM Page: 41 of 144 01I31IO7

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.-L--- Question 22 Details Question Type: Multiple Choice Topic: N-ILT-1540-5-004 Unit 2 was at 100% power when an unidentified leak into the primary containment System ID: 1284 User ID: N-ILT-1540-5-004 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295009AK2.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.1 / SRO 3.2 Cognitive-Level: High

References:

OT-I 00 Justification:

A. Correct B. Incorrect - Condition is a 45% runback.

C. Incorrect - Condition is a 30% runback.

D. Incorrect - Condition is a 45% runback.

. , I Page: 42 of 144 01131I07 NRC EXAM

EXAMINATION ANSW 7 I

. I v-23 ID:N-IL"T-5007-8-006 Points: 1.00.

T h e following Unit 3 conditions exist:

The reactor is at full power.

Torus Cooling is in operation using the 3A and 3C RHR pumps.

HPCI testing is in progress per ST-0-023-301-3, "HPCI Pump, Valve, Flow and Unit Cooler Functional and In-Service Test".

The minimum Torus temperature that requires entry into T-102 "Primary Containment Control" is II) , and the minimum Torus temperature that requires immediately placing t h e mode switch in shutdown is (2) .

A. (1) 95OF

{2)100°F B. - (1) 95'F (2) 11O°F C. (1) 105OF (2) 110°F D. (1) llO°F (2) 12OoF

'v Answer: B NRC EXAM Page: 43 of 144 01131lo7

Question 23 Details Question Type: Multiple Choice Topic: N-ILT-5007-8-006 The following Unit 3 conditions exist:

The reactor is at full power.

Torus Coo System ID: 1285 User ID: N-ILT-5007-8-006 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

29501$AA2.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 1 SRO 4.0 Cognitive-Level: Memory

References:

ST-0-023-301-3 Justification:

I A. Incorrect - While 95OF is an entry for T-102, I

Tech Spec requires reactor mode switch to shutdown position if suppression pool

I temperature > llO°F and 5 12OoF.

1 B. Correct - 95OF is the entry for T-102. T.S.

3.6.2.1 requires immediate suspension of all testing that adds heat to the suppression pool at pool temperature of > 105OF AND to immediately place the reactor mode switch in the shutdown position if suppression pool temperature > 110°F and 5 120°F.

C. Incorrect - 95OF is the entry for T-102. Tech Spec requires reactor mode switch to shutdown position if suppression pool temperature > llO°F and 5 120°F.

D. Incorrect - 95OF is the entry for T-102. Tech Spec requires immediate suspension of all testing that adds heat to the suppression pool at pool temperature of > 105OFAND to immediately place the reactor mode switch in the shutdown position if suppression pool temperature > 110°F and 5 120°F.

i NRC EXAM Page: 44 of 144 0I/31/07

--- 24 ID: N-ILT-1550-4 2A-001 Points: 1.00

Unit 3 is at 100% power at time 11:25 AM when the '3A' Control Rod Drive (CRD) pump trips on overcurrent.

The "38" CRD pump was previously blocked for maintenance.

At time 11:33 AM, multiple accumulator trouble lights illuminate on the Full Core Display for withdrawn control rods.

At time 11:37 AM, CRD Charging Header pressure drops below 940 psig.

In accordance with ON-107, "Loss of CRD Regulating Function", based on the above conditions, you are required to perform a -(I)- at time -(2)- .

A. (1) Manual Scram, enter T-100 (2) 1153 AM B. (1) Manual Scram, enter T-100 (2) 11:57 AM C. ( I ) GP-9 Fast Power Reduction (2) 11:53 AM D. (1) GP-9 Fast Power Reduction (2) 11:57 AM Answer: B NRC EXAM Page: 45 of 144 01I31I07

Question24 Details Question Type: Multiple Choice Topic: N-ILT-1550-12A-001 Unit 3 is at 100% power at time 1125 am the '3A' Control Rod Drive (CRD) pump System ID: 1286 User ID: N-ILT-1550-12A-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295022 G2.1.23 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.9 / SRO 4.0 Cognitive-Level: High

References:

ON-107, Tech. Spec. 3.1.5 Justification:

A. Incorrect - This is 20 minutes from accumulator alarm only, scram not yet required per ON-I07 or Tech Specs 3.15.

B. Correct - 20 minutes to restore charging header pressure once the condition of both multiple accumulator trouble alarms low ( e 940 psig) CRD charging header pressure. This agrees with Tech Spec 3.1.5.

C. Incorrect - This is 20 minutes from accumulator alarm only fast power reduction not required per ON-I07 or Tech Spec 3.1.5.

D. Incorrect - ON-I07 requires a scram due to both conditions (accumulator trouble alarm low charging header pressure).

NRC EXAM Page: 46 of 144 0 1/31107

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Question 25 Details Question Type: Multiple Choice Topic: N-ILT-1560-11-007 Which of the following sets of conditions allows operation of the "A' loop of RHR System ID: 1287 User ID: N-ILT-1560-11-007 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295029EA1.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.9 / SRO 3.0 Cognitive-Level: High

References:

T-102, Sheet 3 Justification:

A. Incorrect - This does not meet the criteria of the RHR NPSH curves for two-pump operation at all flow rates, as shown on T-102, Sheet 3.

Operation is in the unsafe region of the curve when flow is above -23,000 gpm.

8. Incorrect - This does not meet the criteria of the RHR NPSH curves for two-pump operation at all flow rates, as shown on T-102, Sheet 3.

Operation is in the unsafe region of the curve when flow is above -23,000 gpm.

C. Incorrect - This does not meet the criteria of the RHR NPSH curves for two-pump operation at all flow rates, as shown on T-102, Sheet 3.

Operation is in the unsafe region of the curve when flow is above -23,000 gpm.

D. Correct - This meet the criteria of the RHR NPSH curves for two-pump operation at air flow rates, as shown on T-102, Sheet 3.

NRC EXAM Page: 48 of 144 01/31/07

71 8 C I

Question26 Details Question Type: Multiple Choice Topic: N-ILT-1560-3-003 Unit 3 plant conditions are as follows: Reactor is shutdown, RPV level is -30 inche System ID: 1288 User ID: N-ILT-1560-3-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295032EK1.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.6 / SRO 3.8 Cognitive-Level: High

References:

ARC 20221 0 D-4, T-222, T-I 03 Justification:

t A. Correct - T-103 Leg S C K will require a GP-15 local evacuation (SCK-5) for personnel protection and safety and to operate RB and Refuel Floor ventilation using T-222 if building radiation levels can be maintained < 10mRlhr (SC/T-6).

B. Incorrect - T-I 12, Emergency Blowdown will not be required until the same parameter exceeds an action level in more than one area.

There are no areas at an action level at present.

C. Incorrect - T-I 12, Emergency Blowdown will not be required until the same parameter exceeds an action level in more than one area.

There are no areas at an action level at present.

D. Incorrect - RClC and Torus Room temperature would have to reach 135°F for both areas action level to be reached. There are no areas at an action level at present. Two areas at or above an action level are needed in order to perform a T-I 12, Emergency Blowdown, per T-103.

W NRC EXAM Page: 50 of 144 01131 IO7

27 ID: N-ILT-1560-3-064 Points: 1.00 While Unit 2 is operating at 100% power, the following conditions exist

The watertight door between HPCl and RClC was left open with a hose running through the door.

HPCl PUMP ROOM FLOOD alarm is in (221 A-5)

RCIC PUMP ROOM FLOOD alarm is in (222 A-4)

HPCl Room water level IS3 0 feet

RClC Room water level IS 3 0 feet The Equipment Operator reports that the water input is due to a gross packing leak on MO-2 17 HPCl "COND TANK SUCTION".

Which of the following statements are TRUE?

1. T-I 12, "Emergency Blowdown" is entered.

2. SE-9, "Radioactive Liquid Spill" is utilized.

3. The suction line with the leak is to be isolated and a local evacuation should be performed per GP-15.

4. The suction line with the leak is to be isolated and a GP-4, "Scram", and normal RPV depressurization is required.

.~

.--- , A. 1& 2 B. 1&3 C. 2&4 D. 2&3 Answer: D NRC EXAM Page: 51 of 144 01I31I07

EXAMI'NATIONANSW Rev 3 Question 27 Details Question Type: Multiple Choice Topic: N-ILT-1560-3-004While Unit 2 is operating at 100%

power, the following conditions exist:

HPCl System ID: 1289 User ID: N-ILT-1560-3-004 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: I.oo Cross

Reference:

295036EK3.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 / SRO 3.9 Cognitive-Level: High

References:

T-103 Justification:

A. Incorrect - T-103 requires a T-I 12 Blowdown (SCC-IO) only if a primary system is discharging into the reactor building (SCC-7) and the water level reaches an action level in more than one area. HPCI and RClC are considered the same area per T-103. A leak from the Condensate Storage tank (CST) is NOT a primary system leak.

B. Incorrect - T-103 requires a T-I12 Blowdown (SCC-IO) only if a primary system is discharging into the reactor building (SCC-7) and the water level reaches an action level in more than one area. HPCl and RClC are considered the same area per T-103.

C. Incorrect - T-103 requires a GP-4 scram and a depressurization (SCC-8) only if the leak is a primary system discharging into the Reactor Building (SCC-7). A leak from the Condensate Storage tank (CST) is NOT a primary system leak.

D. Correct - Per T-103, "Secondary Containment Control", water level above an alarm level (6" for HPCI/RCIC/Sump Rooms), GP-15, "Local Evacuation" (SC/L-5) and reference to SE-9, "Radioactive Spill" (SC/L-6) are required to be performed.

NRC EXAM Page:52 of 144 01I31107

ID: N-ILTdOl0-6B-003 0 Following 400 days at rated power, Unit 2 is Shutdown with a cooldown in progress.

Reactor Pressure is currently 420 psig.

An electrical transient occurs resulting in the following:

Loss of 125 VDC power to the A logic of RHR.

Loss of Drywell Cooling and a small steam leak cause a rise in Drywell Pressure to 2.2 psig.

Which of the following describes the response of the RHR pumps?

A. All RHR pumps are running, and they are injecting into the vessel B. All RHR pumps are running, and they are NOT injecting into the vessel.

C. Only the B & D pumps are running, and they are injecting into the vessel.

D. Only the B & D pumps are running, and they are NOT injecting into the vessel.

Answer: B NRC EXAM Page: 53 of 144 01131lo7

S 1

QuesOon 28 Details Question Type: Multiple Choice Topic: N-ILT-5010-6B-003Following a 400 day run at power, Unit 2 is Shutdown with a Cooldown in progress.

System ID: 1151 User ID: N-ILTdOI0-68-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: I.oo Cross

Reference:

203000 K2.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.7 / SRO 2.9 Cognitive-Level: High

References:

SO 10.7.B-2 Justification:

A. Incorrect - Reactor pressure is too high for LPCl injection.

B. Correct - RHR logics are cross-divisionalized such that a loss of one 125 VDC supply does not impact LPCl pump starts (unlike Core Spray). Per TRIPS, RHR pump shutoff head is 305 psig so they are not injecting.

C. Incorrect - Even with loss of A logic 125 VDC, all LPCl pumps are running.

D. Incorrect - Even with loss of A logic 125 VDC all LPCl pumps are running.

NRC EXAM Page: 54 of 144 01131107

a :JaMsuV duestion 29 Details Question Type: Multiple Choice Topic: N-ILT-5010-40-003 Unit 2 is in a forced outage with the ' A Loop of SDC in service using the 'C' RHR System ID: 1158 User ID: N-ILT-5010-40-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

205000 K4.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 /SRO 3.8 Cognitive-Level: High

Reference:

PLOT5010.040; GP-8.B; GP-8.B COL Justification:

A. Incorrect - MO-25A (RHR Injection valve) will also close on PClS Group I I signal of 5 +I" RPV level with MO-17 open and MO-18 open and RPV pressure 5 70 psig.

B. Incorrect - MO-17 and MO-18 will close on PClS Group II isolation signal of 5 +I" RPV level.

C. Incorrect - MO-17 and MO-18 will close on PClS Group I I isolation signal of 5 +I"RPV level. The C RHR pump will trip when either MO-17 or MO-18 indicate not full open.

D. Correct - MO-17 & 18 will close on the PClS Group II isolation signal of 5 +I" RPV level with MO-17open and MO-18 open and RPV pressure 5 70 psig.

NRC EXAM Page: 56 of 144 01131lo7

Ll' 30 ID: N-ILT-15303-004 Points: 1.00 Unit 3 is in MODE 3 with RPV coolant temperature at 28OoF. Per procedure GP-12, Core Cooling, the operator must either:

Operate one RHR pump in shutdown cooling OR

Operate one recirc pump OR

Maintain reactor level above +50 inches What is the reason for maintaining water level above +50 inches?

This level:

A. Provides for adequate level to prevent uncovering the core if a reactor coolant leak develops.

B. Provides for natural circulation between the core and the annulus region since no forced cooling flow exists.

C. Provides for a sufficient volume of water to ensure core cooling via conductive heat transfer.

D. Provides for sufficient RPV water level to satisfy Technical Specification 3.9.6 "RPV Water Level" requirements.

Answer: B NRC EXAM Page: 57 of 144 01131107

Question 30 Details Question Type: Multiple Choice Topic: N-ILT-1530-3-004 Unit 3 is in MODE 3 with RPV coolant temperature at 280F. Per procedure GP-I 2, System ID: 1152 User ID: N-ILT-1530-3-004 Status: Active '

Always select on test: No Authorized for practice: No Difficulty: 2.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

205000A4.06 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 / SRO 3.7 Cognitive-Level: Memory

References:

GP-12 Justification:

A. Incorrect - +50 inches does not provide for adequate RPV level to prevent uncovering the core during a LOCA. This answer is describing the function of the PClS RPV Water Level Low (Levels I,2 and 3) signals to ensure that offsite dose limits of 10CFR100 are not exceeded.

6. Correct - Raising RPV level to 2 +50" promotes natural circulation between the core and the annulus region.

C. Incorrect - The volume of water in the RPV at

+50 inches is not sufficient to provide for long-term (shutdown) core cooling. RPV water temperature will rise.

D. Incorrect - Tech. Spec. 3.9.6 requires RPV level to be at least +458 inches above instrument zero during refueling operations.

NRC EXAM Page: 58 of 144 01131IO7

a :JBMS Utj

32 ID: N-ILT-5014-6C-001 '. Point&: f.00 Unit 3 was operating at 100°/~power when a plant transient resulted in the following conditions.

The Reactor is scrammed; all rods are inserted.

Reactor water level -180 inches.

Reactor pressure is 300 psig.

Torus temperature is 185OF.

Torus pressure is 2 psig

Torus level is 11.5 feet

The "A' Core Spray pump is the only pump available for injection Based on these conditions, the "A" Core Spray oump A. CANNOT be used per procedure, the NPSH Limit has been exceeded.

B. CANNOT be used per procedure, the Vortex Limit has been exceeded.

C. CAN be used per procedure, the NPSH and Vortex Limits can be exceeded.

D. CAN be used per procedure, the NPSH and Vortex Limits have been exceeded. I Answer: C NRC EXAM Page: 61 of 144 01/31/07

Question 32 Details Question Type: Multiple Choice Topic: N-ILT-5014-6C-001 Unit 3 was operating at 100%

power when a plant transient resulted in the followin System ID: 1290 User ID: N-lLT-5014-6C-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

209001A1.05 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.5 / SRO 3.6 Cognitive-Level: High

References:

T-101, T-102, T-I 11 Justification:

A. Incorrect - Although the NPSH limit has been exceeded, the A Core Spray pump can be placed in service as directed by Step LR-7 of T-111,

3. Incorrect - The Vortex limit (10.5 feet in the torus) has not been exceeded.

C. Correct - The given conditions result in entry into T-1 11, Level Restoration. Step LR-7 of T-111 allows operation of Core Spray pump A even if the NPSH and/or Vortex limit(s) have been exceeded. The Core Spray pump would start to inject at an RPV pressure of 5 330 psig.

D. Incorrect -The NPSH limit has been exceeded.

NRC EXAM Page: 62 of 144 01/31/07

.4 33 ID:N-ILT-5011-lE-003 Points: 1.60 Unit 2 scrammed from 100% power due to a loss of vacuum and is experiencing an ATWS.

Current plant conditions are as follows:

Reactor power is 37%

RPV level is +23 inches and steady 0 RPV pressure is 950 psig and is being controlled via SRVs.

0 Torus temperature is 95' F and rising.

The CRS has directed the URO to inject Standby Liquid Control (SBLC). The URO positions the SBLC switch to "Pump A Run".

Which of the following is the correct plant response to the above action?

A. 'A'SBLC pump discharge pressure will rise to 1450 psig B. The amber Squib Valve Continuity lights will extinguish C. Only one Squib Valve fires to align a flowpath from SBLC to the Reactor D. GROUP 11/111 INBOARD AND OUTBOARD ISOLATION RELAYS NOT RESET alarms will illuminate.

Answer: D NRC EXAM Page: 63 of 144 01/31/07

Question33 Details Question Type: Multiple Choice Topic: N-ILT-5011-1E-003Unit 2 scrammed from 100% power due to a loss of vacuum and is experiencing an ATW System ID: 1364 User ID: N-ILT-5011-1E-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: I.oo Cross

Reference:

21 1000 K4.07 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 / SRO 3.9 Cognitive-Level: Memory

References:

SO 11.I .B-2, PLOT 5011 Justification:

A. Incorrect - This is the system RV setpoint. System discharge pressure should be approx. 100 psig above reactor pressure.

B. Incorrect - Lights are lit until SBLC pump control switch is taken to Offposition.

C. Incorrect - Both squib explosive valves fire when either SBLC pump is started from the MCR.

D. Correct - due to RWCU isolation on SBLC initiation.

NRC EXAM Page:64 of 144 01131lO7

'3

Question34 Details Question Type: Multiple Choice Topic: N-ILT-5060F-26-002 Unit 2 conditions:

Reactor power is 100%.

Both RPS Busses were aligned to System ID: 1162 User ID: N-lLT-5060F-2B-002 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

212000 K2.01 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.2 I SRO 3.3 Cognitive-Level: Memory

Reference:

PLOT 5060F; SO 54.7.A A. Incorrect - 4 kV bus will transfer in 0.25 seconds, but there is another 3 seconds until the Emergency Bus MCC is reenergized.

B. Correct - The 4KV bus will fast transfer in 0.25 seconds, then 3 seconds later the Emergency Bus MCC will reclose providing 480 VAC power back to the RPS MG Set. No RPS half scram will occur.

C. Incorrect - 8 seconds corresponds to the time delay before the RPS MG Set Supply Breakers trip on a loss of power. This would result in a half scram.

D. Incorrect - 13 seconds corresponds to 10 seconds for the EDG to start and 3 additional seconds for emergency Bus MCC to reenergize. The 8 second time delay trip is designed to cause a loss of RPS (and scram) rather than allowing the system to continue operation after a complete loss of off-site power. This would result in a half scram.

NRC EXAM Page: 66 of 144 01I31107

Question 35 betaits Question Type: Multiple Choice Topic: N-ILT-5060C-4A-006 A Unit 2 Reactor startup is in progress

The required critical data documentatio System ID: 1164 User ID: N-ILT-5060C4A-006 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

215003 K1.O1 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.9 / SRO 3.9 Cognitive-Level: High

Reference:

PLOT 5060C: ARCS 21 IB-I and 21 1 C-I Justification:

A. Correct - INOP failure is a "trip" signal. One in each trip system will generate a full scram, the "HighANOP' annunciator, and a control rod block. The WRNM System trips are bypassed only in Mode I.

B. Incorrect - A full scram will result from a trip signal in each channel.

C. Incorrect - INOP failure is a "trip" signal. One in each trip system will generate a full scram, the "HighANOP' annunciator, and a control rod block.

D. Incorrect - INOP failure is a "trip" signal. One in each trip system will generate a full scram, the "HighANOP' annunciator, and a control rod block.

NRC EXAM Page: 68 of 144 01/31/07

36 [D: N-ILT-5066C4A-005 Points: 1.60

A Unit 3 reactor startup and approach to critical is in progress.

During a rod withdrawal from position '20' to '22', a high notch worth causes alarm 310 F-3, WRNM SHORT PERIODTTROUBLE, as detected by WRNM Channel G.

The URO confirms a period of 25 seconds.

In accordance with procedure GP-2 "Normal Plant Startup", which of the following, if any, is the required operator action?

A. NO additional operator action required for this condition.

B. INSERT the control rod to the full-in position.

C. INSERT the control rod to lengthen period to > 50 seconds.

D. INSERT the control rod to lengthen period to infinity.

Answer: C NRC EXAM Page: 69 of 144 01131107

S 1

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Question 36 Details Question Type: Multiple Choice Topic: N-ILT-5060C-4A-005 A Unit 3 reactor startup and approach to critical is in progress. During a rod System ID: 1154 User ID: N-ILT-5060C-4A-005 Status: Active Always select on test: No Authorized for practice: No DifficuIty: 3.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

215003 G2.4.50 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 / SRO 3.3 Cognitive-Level: Memory

References:

ARC 2(3)10-F-3, GP-2 Justification:

A. Incorrect - A reactor period of 5 28 seconds will initiate a control rod withdraw block. Procedure GP-2, startup, provides guidance to manipulate control rods to ensure that the reactor period does not go less than 50 seconds.

B. Incorrect - A reactor period of 5 28 seconds will initiate a control rod withdraw block. Procedure GP-2, startup, provides guidance to manipulate control rods to ensure that the reactor period does not go less than 50 seconds.

C. Correct - A reactor period of 5 28 seconds will initiate a control rod withdraw block. Procedure GP-2, startup, provides guidance to manipulate control rods to ensure that the reactor period does not go less than 50 seconds.

D. Incorrect - A reactor period of 5 28 seconds will initiate a control rod withdraw block. Procedure GP-2, startup, provides guidance to manipulate control rods to ensure that the reactor period does not go less than 50 seconds.

NRC EXAM Page: 70 of 144 0 1I31 lo7

Question 37 Details Question Type: Multiple Choice Topic: N-ILT-5060-3A-005 With Unit 2 operating at 25%

power, the #2 APRM fails donwscale (not INOP).

Which System ID: 1166 User ID: N-ILT-5060-3A-005 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

215005 K3.03 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 I SRO 4.0 Cognitive-Level: High

Reference:

PLOT 5060, ARC 21 1 C-2 Justification:

A. Incorrect - APRM downscale (23.2 %) in MODE 1 will generate a control rod withdraw block and downscale alarm 21 1 C-2 only.

B. Incorrect - A scram vote signal is only generated for :

APRM h o p Trip High Neutron Flux Simulated Thermal Power High C. Incorrect - A scram vote signal is only generated for :

APRM lnop Trip High Neutron Flux Simulated Thermal Power High D. Correct - APRM downscale (53.2 %) in MODE 1 will generate a control rod withdraw block and downscale alarm 21 1 C-2 only.

NRC EXAM Page: 72 of 144 01I31 I07

tion 38 Details Question Type: Multiple Choice Topic: N-ILT-5002-1W-001 The reactor recirculation flow comparators have a 10% mismatch alarm, APRM FLOW System ID: 1291 User ID: N-ILT-5002-1W-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

215005A3.06 User Text:

User Number I: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.0 / SRO 3.1 Cognitive-Level: Memory

References:

ARC 21 1 A-4 Justification:

A. Incorrect - A Recirc loop and B Recirc loop flows are NOT compared to each other. The flow comparator 10% alarm is based on the difference between any of the four APRM total drive flow values.

B. Incorrect - There is no average recirc loop flow signal.

C. Correct - Recirc loop flow comparator alarm setpoint is based on > 10% difference between any of the four APRM total drive flow values.

D. incorrect - There is no comparator circuit between total recirc flow and the recirc MG Set speed demand.

NRC EXAM Page: 74 of 144 01/31/07

a Ja M S Ut/

I

40 a ID:N-ILT-BO13-~B-001 . Points: 1.00 The following conditions exist on Unit 2:

A spurious PClS Group I isolation has occurred.

RPV level lowered to -40 inches and was restored with RCIC.

RPV level is presently steady at +30 inches.

The PRO placed RCIC in the CST-to-CST mode per RRC 13.1-2, "RCIC System Operation During a Plant Event".

Which of the following actions are required in order to re-inject with RClC per RRC 13.1-2, "RCIC System Operation During a Plant Event"?

A. Throttle close MO-2-23-24, Condensate Tank Return, until RClC system discharge pressure is at least 100 psig greater than reactor pressure AND AO 13-22,Discharge Check, indicates open.

B. Increase RClC turbine speed by adjusting the RClC flow controller to maintain RClC system discharge pressure at least 100 psig greater than reactor pressure AND AO-2-13-22, Discharge Check, indicates open.

C. Throttle close MO-2-13-30, Full Flow Test, until RClC system discharge pressure is at least 100 psig greater than reactor pressure AND AO-2-13-22, Discharge Check, indicates open.

D. Throttle open MO-2-13-30, Full Flow Test, until RCIC system discharge pressure is at least 50 psig greater than reactor pressure &@ AO-2-13-22, Discharge Check, indicates split indication.

Answer: C NRC EXAM Page: 77 of 144 01/31107

AN RO Rev Question 40 Details Question Type: Multiple Choice Topic: N-ILT-5013-5B-001 The following conditions exist on Unit 2: *A spurious PClS Group I isolation has System ID: 1294 User ID: N-ILT-5013-5B-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

217000A4.07 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.9 / SRO 3.9 Cognitive-Level: High

References:

RRC 13.1-2 Justification:

A. Incorrect - MO-2-23-24 is placed full open in the CST-to-CST mode and is left full open even when subsequent RPV injection is required.

\___.- B. Incorrect - RRC 13.1-2 does not refer to using speed adjustments for controller RPV re-injection.

C. Correct - Per RRC 13.1-2, if subsequent vessel injection is required once in the CST-to-CST mode, then throttle close MO-30, Full Flow Test, until RClC discharge pressure is at least 100 psig greater than reactor pressure AND AO-22, Discharge Check, is open.

D. Incorrect - The MO-2-13-30, Full Flow Test, must be throttled close in order to raise RClC system pressure greater than RPV pressure.

Throttling open MO-30 will only lower RClC system pressure.

-e-NRC EXAM Page: 78 of 144 01131J07

41 ID:N-ILT-5001G6-005 Points: 1.00 The Automatic Depressurization System (ADS) will actuate on which of the following conditions?

A. Drywell pressure at 4.1 psig Reactor water level at -1 20 for 10 minutes A and DCore Spray Pumps operating B. Drywell pressure at 5.0 psig Reactor water level at -165 for 5,minutes A and 8 Core Spray Pumps operating C. Drywell pressure at 1.2 psig Reactor water level at -165 for 5, minutes BRHR Pump operating D. Drywell pressure at 2.7 psig Reactor water level at -165 for 3 minutes D RHR Pump operating Answer: D NRC EXAM Page: 79 of 144 01/31/07

Question 41 Details Question Type: Multiple Choice Topic: N-ILT-5001G-5-005 Which one of the following plant conditions will directly result in the initiation System ID: 1170 User ID: N-ILT-5001G-5-005 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1 .oo Cross

Reference:

218000K5.01 User Text: B User Number 1: 0.00 User Number 2: 3.00 Comment: Importance: RO 3 . 8 / SRO 3.8 Cognitive-Level : High

References:

M-1-S-52;ARC 227 D-4 Justification:

A. Incorrect - Rx level does not reach triple Lo level

-160".

B. Incorrect -The right combination of ECCS pumps is not available. (Need A or B and C or D Core Spray pumps)

C. Incorrect - DNV pressure is too low and the time is not long enough. (Need 9.5 minutes)

D. Correct - logic is satisfied.

NRC EXAM Page: 80 of 144 0 1/31/07

Question 42 Details Question Type: Multiple Choice Topic: N-ILT-5007G-3Q-001 Given the following: *Unit 2 is operating normally at 100% power. *Reactor Buil System ID: 1295 User ID: N-ILT-5007G-3Q-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

223002K3.18 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.0 / SRO 3.1 Cognitive-Level: High

References:

GP-8.D, M-1-S-23, E-277,E-278 Justification:

A. Incorrect - This choice indicates RBV remains in service.

B. Incorrect - This choice indicates RBV trips, SGTS starts and maintains the same Reactor Building d/p.

C. Correct - A PClS Group Ill half isolation causes Reactor Building Ventilation (RBV) to trip and isolate, and SGTS to auto-start. Since SGTS is required by design (and Tech Spec 3.6.4.1) to maintain Reactor Building d/p 2 0.25 inches of vacuum WG, Reactor Building d/p will become more negative when SGTS starts.

D. Incorrect - This choice indicates RBV trips and SGTS either does not start or maintains a less negative Reactor Building d/p.

NRC EXAM Page: 82 of 144 01131107

.4 ID:NilLT-5007G-5D-003 A plant startup is in progress on Unit 2 The following conditions exist 0 The Reactor Mode Switch is in STARTUP.

0 Two Turbine Bypass Valves are open.

0 Reactor pressure is 940 psig and steady.

Which one of the following describes the plant response, if any, if "PCIS System I Main Steam Line High Flow" differential pressure transmitter DPT-2-118A fails high?

A. No effect since the Mode Switch is NOT in RUN B. ONLY a Half Group I isolation will occur.

C. ONLY a Full Group I Isolation will occur.

D. a Full Group I Isolation AND a reactor scram will occur Answer: E3 NRC EXAM Page: 83 of 144 01/31/07

d Question 43 betaiis Question Type: Multiple Choice Topic: N-ILT-5007G-5D-003 A plant startup is in progress on Unit 2. The following conditions exist:

System ID: 1365 User ID: N-ILT-5007G-5D-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

223002 2.1.27 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 I SRO 3.5 Cognitive-Level: High

References:

PLOT 5007G, ARC 21 1 H-I Justification:

A. Incorrect - a half Group I isolation will occur. This Group I signal is not Mode Switch dependent.

B. Correct - a half Group I isolation will occur only C. Incorrect - a half Group I isolation will occur only.

D. Incorrect - a half Group I isolation will occur only.

No reactor scram will occur.

NRC EXAM Page: 84 of 144 01131107

Question 44 Details Question Type: Multiple Choice Topic: N-ILT-5001A-4D-003 During a high reactor pressure transieyt on Unit 2, the Plant Reactor Operator System ID: 1155 User ID: N-ILT-5001A-4D-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

239002K5.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.4 / SRO 3.5 Cognitive-Level: High

References:

Tech. Spec. 3.4.3 Justification:

A. Incorrect - if 1135 psig was the peak pressure only 4 SRVs would have the white memory lights lit.

B. , Correct - SRV setpoints range form 1135 psig to 1155 psig. If all 11 white memory light are lit, then pressure reached 1155 psig. With only the C & DSRVs still open, pressure is at lowest range value of 1135 psig.

C. Incorrect - 1260 psig is the setpoint for safety valve (not SRV) actuation.

D. Incorrect - 1325 psig is the reactor coolant system pressure safety limit.

NRC EXAM Page: 86 of 144 01I31lo7

-*-- "45 b* . ID: N-ILT-50063Jb01 Points: 1.00' Given the following:

Unit 3 is operating at 100% power.

A "Feedwater Controller Failure - Maximum Demand" transient occurs as described in the Updated Final Safety Analysis Report (UFSAR).

RPV water level rises at a rate of 2 inche4sper second.

Assuming no operator actions, one minute later the reactor recirculation pumps are:

A. Tripped.

B. Operating at 30% speed.

C. Operating at 45% speed.

D. Operating at the initial speed Answer: A NRC EXAM Page: 87 of 144 0 1I31lo7

Question 45 Details t Question Type: Multiple Choice Topic: N-ILT-5006-3J-001 Given the following: *Unit 3 is operating at 100% power. *A "Feedwater Controll System ID: 1297 '

User ID: N-lLT-5006-3J-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

259002K3.04 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.9 / SRO 3.0 Cognitive-Level: High

References:

UFSAR 14.5.2.2, UFSAR Figure 14.5.5, PLOT-A610 Objective 1 Justification:

A. -

Correct With no operator actions and RPV level rising at least Z"/second, RPV level will reach the high level turbine trip setpoint (+46")

in approximately 10 seconds. A turbine trip from full power will result in high reactor pressure and SRV actuations. This transient, as analyzed in Section 14.5.2.2 of the UFSAR results in a peak reactor pressure of -1250 psig (at the bottom of the vessel). An ATWS-RPT will occur at 1106 psig...approximately 13 seconds into the event.

B. Incorrect - Recirc pumps trip on high reactor pressure.

C. Incorrect - Recirc pumps trip on high reactor pressure.

D. Incorrect - Recirc pumps trip on high reactor pressure.

NRC EXAM Page: 88 of 144 01I31IO7

Question 46 Details Question Type: Multiple Choice Topic: N-ILT-5009A-3A-005 Unit 3 is operating at 100% power when a valid Group Ill PClS signal is System ID: 1172 User ID: N-ILT-5,009A-3A-005 Status: Active ,

Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

261000A3.03 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: ImportAnce: RO 3.2 / SRO 3.3 Cognitive-Level: High

Reference:

PLOT 5009A Justification:

A. Incorrect - results in high SBGT flow with a less negative DP.

B. Incorrect - results in normal SBGT flow with a

. -. ' less negative or possible positive DP.

C. Correct - Bypass damper PO-00522 provides for minimum flow recirculation path of approx -

20% for capacity back to suction plenum. It needs to reposition to ensure R B + Refuel Floor can be maintained at a negative pressure.

D. Incorrect - results in high SBGT flow with more negative DP.

NRC EXAM Page: 90 of 144 01/31/07

S 1

Question 47 Details Question Type: Multiple Choice Topic: N-ILT-5051-6-001 Unit 2 and Unit 3 are at 100%

power. Using a single line diagram of the North and S System ID: 1344 User ID: N-ILT-5051-6-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.50 ,

Time to Complete: 2 Point Value: 1.oo Cross

Reference:

262001 K4.04 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.8 I SRO 3.1 Cognitive-Level: High

References:

Print E-I, Station Single Line I

EXAMINEE MUST HAVE A COPY OF PRINT E-I IN ORDER TO ANSWER THIS QUESTION.

Justifiyation:

A. Incorrect - 65 Breaker is a Unit output breaker and does not have a reclosure feature. Also, for a fault on the 5010 Line the 55 Breaker would trip open as well.

B. Correct - Breakers 55 and 65 will open on the fault and only the 55 Breaker will attempt reclosure. 65 Breaker is a Unit output breaker and does not have a reclosure feature.

C. Incorrect - The Unit 3 Main Generator will not lockout. Output Breaker 15 will remain closed.

D. Incorrect - Breakers 55 and 65 will open on the fault.

The 55 and 65 Breaker motor operated disconnects are manually operated ONLY.

I NRC EXAM Page: 92 of 144 01131107

.=--..

'-4' Question 48 Details Question Type: Multiple Choice Topic: N-ILT-5058-5C-003

The 20Y050 supply from the Static Inverter is in a normal lineup.

A fault occ System ID: 1156 User ID: N-ILT-5058-5C-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.50 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

262002K4.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.11SRO 3.4 Cognitive-Level: High

References:

ARC-220 F-5 Justification:

A. Incorrect - The Static Switch will transfer to alternate source in order to maintain 20Y050 panel energized.

B. Incorrect - The Static Switch will transfer to alternate source in order to maintain 20Y050 panel energized.

C. Correct - The Static Inverter is current limited.

- If a fault develops it will automatically transfer to the Alternate Source which can supply the larger current necessary to clear the fault and then transfer back to normal DC supply when fault clears.

D. Incorrect - The Static Switch will transfer to the alternate source in order to maintain 20Y050 panel energized.

NRC EXAM Page: 94 of 144 01131107

I Question 49 Details I Question Type: Multiple Choice Topic: N-ILT-5057-6A-002Given the following conditions on Unit 2: *2A 1251250 Volt Battery Charger has System ID: 918 User ID: N-ILT-5057-6A-002 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

263000 K6.01 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.2 / SRO 3 5 Cognitive-Level: High Referehce: SO 57B. 1-2 Justification:

A. Incorrect - the charger will return to the equalize charge mode.

B. Correct - from Note 2 in SO 57B.1-2 "Upon a loss of AC input power, the battery charger will return to the same mode it was in once power is restored. IF the battery charger was in the Equalize mode, THEN the timer will pick up where it was interrupted AND time out."

C. Incorrect - the 2A battery charger is a safety-related component and is automatically restored approximately 16 seconds after the diesel generator restores power to the emergency bus.

D. Incorrect - the 2A battery charger is a safety-related component and is automatically restored approximately 16 seconds after the diesel generator restores power to the emergency bus.

NRC EXAM Page: 96 of 144 01131107

'\.-.' '

Qukstton 50 'Details Question Type: Multiple Choice Topic: N-ILT-5057-1D-001 Unit 2 was operating at full power when the following occurs: 2AD004/2BD004 BATTE System ID: 1177 User ID: N-ILT-5057-1D-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

263000A3.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.2 / SRO 3.3 Cognitive-Level: High

References:

A 0 57A. 1-2 Justification:

A. Incorrect - Although the ammeter should approach zero, Ground Lamp indications that are brightly lit indicate a positive ground.

B. Incorrect - Ground Lamp indications that are brightly lit indicate a positive ground and full scale ammeter indicates a significant ground is present.

C. Correct -With no ground present (isolated),

both lights will be dim. Ammeter will read near zero due to low ground current.

D. Incorrect - Although the Ground Light indications should be dimly lit, a full scale ammeter reading indicates a significant ground is present.

NRC EXAM Page: 98 of 144 01I31 IO7

Li 251 ID: N-ILT-5052-6G-004 Points: 1.00 e An electrical fault and blown fuse have resulted in loss of the Unit 3 Div II Station 125V DC distribution panel 30024 (3PPD), which is now de-energized.

A few minutes later, Unit 3 receives a LOCA signal.

What is the effect on the E-2 or E 4 emergency diesel generators?

A. E-2 diesel will not automatically start.

6. E-2 diesel will start but not field flash.

C. E 4 diesel will not automatically start.

D. E 4 diesel will start but not field flash.

Answer: C Question 51 Details Question Type: Multiple Choice Topic: N-ILT-5052-6G-004 An electrical fault and blown fuse has resulted in the loss of the Unit 3 Div II System ID: 1179 User ID: N-ILT-5052-6G-004

--- Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

264000 K6.09 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 I SRO 3.5 Cognitive-Level : High

Reference:

PLOT5052.06G, print E-27 sht 1 Justification:

A. Incorrect - E-2 will start and be available for loading.

6. Incorrect - E-2 will start and be available for loading.

C. Correct - Div II 125 V DC Panel 3 PD supplies the E 4 EDG VDC logic and solenoid power.

E 4 will not start.

D. incorrect - Div II 125 V DC Panel 3 PD supplies the E-4 EDG VDC logic and solenoid power. E 4 will not start.

NRC EXAM Page: 99 of 144 01131107

'a

'3

'a

'if

v/ ID: N-ILT-50346D-001 Given the following:

0 Peach Bottom Unit 2 is operating at 100% power The "A" TBCCW pump trips on an electrical fault.

0 The "6"TBCCW pump is blocked.

Which of the following describes the impact of this event and the associated required action?

A. Due to the imminent loss of Condensate pumps, scram the reactor IAW GP-4, "Manual Scram".

B. Due to the imminent loss of Stator Water Cooling, if Generator load is greater than 7,760 amps, perform GP-4, "Manual Scram".

C. Due to a loss of lsophase Bus Cooling, reduce Main Generator load to less than 18,000 amps IAW GP-9-2, "Fast Reactor Power Reduction".

D. Due to loss of cooling to the Instrument Air compressors, immediately cross-tie the Instrument Air header with Unit 3 IAW ON-I 19, "Loss Of Instrument Air".

Answer: C NRC EXAM Page: 102 of 144 01131107

E

-v-Question 53 Details Question Type: Multiple Choice Topic: N-ILT-5034-6d-001 Loss of Cooling to TBCCW loads Impact on Ops System ID: 1263 User ID: N-ILT-5034-6D-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: I.oo Cross

Reference:

400000A2.01 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 / SRO 3.4 Cognitive-Level: High

Reference:

PLOT 5034, OBJ. 6d; ON-113 & Bases; ON-I 18 & Bases Justification:

A. Incorrect - ON-I 18 directs monitoring Condensate pump bearing and motor oil temperatures and if any temperature is at or above 190 degrees, or if any pump vibration alarm is received, then ON-118 directs reducing reactor power IAW GP-9-2 and removing the affected pump(s) from service.

ON-I 18 does not direct a manual scram due to imminent loss of Condensate pumps.

B. Incorrect - Stator Cooling is cooled by Service Water, not TBCCW.

C. Correct - if TBCCW cannot be restored, ON-118 directs reducing Generator load to less than 18,000 amps IAW GP-9-2. As stated in ON-1 18, isolated bus coolers are not considered vital TBCCW loads; hence a loss of TBCCW and the subsequent isolation of non-vital TBCCW loads, during swap to RBCCW, results in a loss of cooling water to these coolers.

D. Incorrect - with both TBCCW pumps tripped (both breaker contactors open), vital TBCCW loads (CRD pumps and Instrument Air Compressors) will automatically swap to RBCCW after a 40-second time delay.

RBCCW will provide sufficient cooling to Instrument Air Compressors, preventing the need to cross-tie the Unit 2 Instrument Air c- header to Unit 3.

NRC EXAM Page: 103 of 144 01131107

coo-v C-coos-.ni-ru :ai I .

'-4' Question 54 Details Question Type: Multiple Choice Topic: N-ILT-5003-1A-003 Unit 2 is at 70% power to support a control rod pattern adjustment. During a one System ID: 1358 User ID: N-ILT-5003-1A-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

201001 G2.4.31 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 / SRO 3.4 Cognitive-Level: High

References:

SO 62.1 .A-2 WithdrawingAnserting a Control Rod THE EXAMINEE WILL NEED TABLE 2 "CAUSE AND CORRECTIVE ACTION TROUBLE SHOOTING" OF SO 62.1.A-2 IN ORDER TO ANSWER THIS QUEST10N.

Justification:

A. Correct - Drive flow is high. Drive pressure is low.

B Incorrect - Drive flow would be low, drive pressure would be normal.

C. Incorrect - Drive flow would be low.

D. Incorrect - Drive pressure would be normal.

NRC EXAM Page: 105 of 144 01/31/07

3 :.iaMsulj Em I1 .a A~NOEW z 3 AlNO 2 8 AlNO 1 lf

Question 55 Details Question Type: Multiple Choice Topic: N-ILT-5012-6F-001 A startup is in progress on Unit 3 with reactor power at 5%. Panel 30Y34 is inadv System ID: 1299 User ID: N-ILT-5012-6F-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

204000KL6.08 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.5 / SRO 3.5 Cognitive-Level: Memory

References:

GP-8.D, GP-8.C, M-1-S-23; A 0 58A.3-2 Justification:

A. Incorrect - MO-3-12-15 does not close on loss of 30Y34.

B. Incorrect - MO-3-12-68 will also close on loss of 30Y34.

C. Correct - Panel 30Y34 provides power to PCIS outboard isolation valve logic. Loss of 30Y34 will result in isolation of the associated outboard containment isolation valves, including RWCU valves MO-3-12-18 and MO-3-12-68. Note that a loss of Panel 30Y33 causes a loss of power to PClS inboard isolation valve logic. This in turn would result in closure of associated inboard containment isolation valves and, in the case of RWCU, a closure of the outboard containment ;solation valves as well. This is due to loss of power to the NRHX high outlet temperature relay, which feeds both the inboard and outboard RWCU isolation valve logic. Note #2 in GP-8.C and GP-8.D describe the RWCU response to a loss of 20(30)Y33 and 20(30)Y34, respectively.

D. Incorrect - MO-3-12-15 does not close on loss of 30Y34.

NRC EXAM Page: 107 of 144 0 II3 1IO7

E

-J 56 ID: N-ILT-5062-3A-007 Points: 1.00

Unit 2 is at 100% power.

A transient requiring control rod insertion per GP-9-2, "Fast Reactor Power Reduction",

occurs.

Annunciator 21 1 D-5 RPlS INOPERATIVE is received.

Annunciator 21 1 F-5 RWM ROD BLOCK is received.

Continued control rod insertions are:

A. not possible with the exception of a scram condition

6. possible by using the Rod Control Switch held in the "Rod In" position.

C. possible by using the Emergency In/Notch Override Switch in "Emergency In".

D. possible for all control rods with the exception of the rod with the RPIS failure.

Answer: A NRC EXAM Page: 108 of 144 01I31IO7

e.

Question56 Details Question Type: Multiple Choice Topic: N-ILT-5062-3A-007 Unit 2 is at 100% power. A Transient requiring control rod insertion per GP-9-2 System ID: 1181 User ID: N-l LT-5062-3A-007 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1 .oo Cross

Reference:

214000K1.04 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.2/ SRO 3.2 Cognitive-Level: Memory

References:

ARC-21 1 D-5 Justification:

A. Correct - A select block stops all rod movement except scram.

B. Incorrect - Select block from RPIS failure stops all rod movement. The operator cannot even select any control rod for insertion.

C. Incorrect - Select block from RPlS failure stops all rod movement. The operator cannot even select any control rod for insertion.

D. Incorrect - Select block from RPlS failure stops all rod movement. The operator cannot even select any control rod for insertion.

NRC EXAM Page: I09 of 144 01131/07

a :JaMsuv Question 57 Details Question Type: Multiple Choice Topic: N-ILT-5007F-1E-001 A Traversing In-Core Probe trace is being performed using automatic operation.

Svstem ID: 1183 User ID: N-ILT-5007F-1E-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

215001A3.03 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.5 / SRO 2.6 Cognitive-Level: Memory

Reference:

PLOT 5007F; SO 7F.7.A-2 Justification:

A. Incorrect - On a Group II D isolation signal the TIP detector is first retracted to the inshield position and the ball valve closes.

B. Correct - On a Group II D isolation signal the TIP detector is first retracted to the inshield position and the ball valve closes.

C. Incorrect - On a Group II D isolation signal the TIP detector is first retracted to the inshield position and the ball valve closes.

D. Incorrect - Each shear valve must be actuated by a keylock switch located on the TIP console valve control monitor panel.

NRC EXAM Page: 111 of 144 01131107

-J ID: N-ILT&O23-6l~Ol

Unit 2 has experienced a reactor scram from 100% power.

HPCl and RClC initiated on low RPV level.

Reactor level is + 20" and rising quickly.

Subsequently LT-2-02-3-072C, Wide Range Reactor Vessel Water Level, fails downscale.

All other RPV level instruments remain operable.

Assuming no operator action is taken, what is the response, if any, of the HPCl system as RPV level rises?

A. HPCl will trip, but NOT isolate, at RPV level of +29".

B. HPCl will trip, but NOT isolate, at RPV level of +46".

C. HPCl will trip AND isolate at RPV level of +46".

D. HPCl will NOT trip and will NOT isolate on high RPV level of +46' Answer: D NRC EXAM Page: 112 of 144 01I31I07

Question 58 Details a Question Type: Multiple Choice Topic: N-ILT-5023-61-001 "Unit 2 had been operating at 100%

power. *A low level transient occurred causing System ID: 1300 User ID: N-l LT-5023-61-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

216000K3.14 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.8 / SRO 4.2 Cognitive-Level: High

References:

ARC 221 B-I HPCl TURB TRIP Justification:

A. Incorrect - HPCl high RPV level trip setpoint is

+46", not 29". Trip needs input from both LT-72C & LT-72D (2 out of 2 logic).

B. Incorrect - HPCI high RPV level trip needs input from both LT-72C & LT-72D (2 out of 2 logic).

C. Incorrect - HPCl does not isolate at RPV level of +29". RPV level of +29" is the level at which HPCl will restart if tripped at +46" with no operator action.

D. Correct - HPCI RPV high level trip requires input from both LT-72C and LT-72D (2 out of 2 logic}. With one transmitter downscale, the HPCl system will not trip on high level.

NRC EXAM Page: 113 of 144 01/31/07

--- 59 ID:N-ILT-21025A-017 Points: 1.00 Unit 2 was operating at 100% power when a feedwater line break occurred inside containment.

Current plant conditions are as follows:

RPV pressure is 900 psig and lowering.

RPV level is +20 inches and steady.

Torus pressure is 7 psig and rising.

Torus sprays can be initiated IF Torus level is below -(I)- feet. This is because above this level -(2)-.

A. (1) 18 (2) it is assumed the torus spray spargers are submerged and no spray action will occur.

6. (1) 21 (2) it is assumed the torus spray spargers are submerged and no spray action will occur.

C. (1) 18 (2) the torus-to-drywell vacuum breakers are submerged, which could cause the Primary Containment negative design pressure to be exceeded.

D. (1)21 (2) the torus-to-drywell vacuum breakers are submerged, which could cause the

.~

.--- Primary Containment negative design pressure to be exceeded.

Answer: B NRC EXAM Page: 114 of 144 0 1I31I07

.a

'3

'a

'Q

60 ID: N-ILT-5010-2A-001 _. Points: 1.00

Unit 2 is in MODE 4.

The "B" Loop of RHR is lined up to cool the fuel pool per A 0 10.3-2, "RHR System to Fuel Pool Cross-Connect Operation" using the 2D RHR pump.

The "A"Loop of RHR is lined up in shutdown cooling with the 2A RHR pump.

A fault on the E-42 bus results in annunciator 005-B1, E 4 2 BUS DIFFERENTIAL OR OVERCURRENT RELAYS.

The E4 Diesel Generator auto starts and:

A. loads the E42 Bus. Shutdown Cooling remains in service.

B. loads the E42 Bus. Fuel Pool Cboling using 'B' RHR Loop remains in service.

I

~

C. does NOT load the E42 Bus. Shutdown Cooling is lost.

D. does NOT load the E42 Bus. Fuel Pool Cooling using the 'B' RHR Loop is lost.

Answer: D NRC EXAM Page: 116 of 144 01I31IO7

n INATION ANSW 2007 61

- ID: N-ILT-5001DL5A-001 Points: 1.00 I . - -

~

Unit 3 is operating at rated power.

Fully withdrawn control rod 30-31scrams unexpectedly.

Which of the following describes the INITIAL response (within the first 5 seconds) of reactor pressure and Turbine Control Valve position to this transient?

Reactor Pressure TCV Position A. Decreases Open slightly

6. Decreases Close slightly C. Increases Open slightly D. Increases Close slightly Answer: B NRC EXAM Page: 118 of 144 01/31/07

Question 61 Details Question Type: Multiple Choice Topic: N-ILT-5001DL-SA-001 Unit 3 is operating at rated power. A fully withdrawn control rod spuriously sc System ID: 1186 User ID: N-ILT-5001DL-5A-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: I .oo Cross

Reference:

241000K5.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Impodnce: RO 3.5 I SRO 3.6 Cognitive-Level: Memory Referehces:

Justification:

A. Incorrect - As reactor pressure decreases, TCVs will close slightly to maintain the required throttle pressure.

B. Correct - Reactor pressure will decrease with the control rod insertion. As reactor pressure decreases, TCVs will close slightly to maintain the required throttle pressure.

C. Incorrect - Reactor pressure will INITIALLY decrease on control rod insertion (lower power).

D. Incorrect - Reactor pressure will INITIALLY decrease on control rod insertion (lower power).

1 1

1 I

NRC EXAM Page: 119 of 144 01131107

-- 62 , ID: N-lLTS001B4A-009 Points: 1.00 Which of the following identifies the positions of the Turbme Control Valves (TCVs) and Combined Intermediate Valves (CIVs) immediately following a turbine trip7 TCVs -

c IVS A. Closed Open

6. Closed Closed C. Open Open D. Open Closed Answer: B Question 62 Details I Question Type: Multiple Choice Topic: N-ILT-5001BAA-009 Which of the following identifies the expected positin of the Turbine Control System ID: 1187 User ID: N-ILT-5001B-4A-009 Status: Active c- Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

245000A1.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.7 I SRO 2.9 Cognitive-Level: Memory

References:

SO 1B.2.A-2, SO IB.2.A-3 Justification:

A. Incorrect - ClVs will get a close signal on a turbine trip for turbine protection.

B. Correct - TSVs and ClVs will get a close signal on a turbine trip for turbine protection.

C. Incorrect - ClVs will get a close signal on a turbine trip for turbine protection.

D. Incorrect - TCVs will get a close signal on a turbine trip for turbine protection.

NRC EXAM Page: 120 of 144 01/31/07

-' ID:N-lLT5006-61-002 Unit 2 is operating normally at 100% power when:

FEEDWATER FIELD INSTRUMENTTROUBLE (201 H-I) goes into alarm.

"B" main steam line flow indicator Fl-2-06-0888 on Panel 20C08A instantaneously fails downscale.

Which of the following describes the response, if any, of the Digital Feedwater Control System (DFCS)?

DFCS will:

A. remain in three element control and maintain normal RPV water level (+23").

B. remain in three element control and maintain a higher than normal RPV water level.

C. shift to single element control and maintain normal RPV water level (+23").

D. shift to single element control and maintain a lower than normal RPV water level.

Answer: C NRC EXAM Page: 121 of 144 01/31IO7

ION ANS Question 63 Ddails ~

Question Type: Multiple Choice Topic: N-ILT-5006-61-002 Unit 2 is operating normally at 100%

power when: *FEEDWATER FIELD INSTRUMENT TROU System ID: 1302 User ID: N-ILT-5006-61-002 Status: Active Always select on test: No Authorized for practice: NO Difficulty: 3.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

259001A2.07 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.7 I SRO 3.8 Cognitive-Level: High

References:

ARC 201 H-I . OT-100 Justification:

A. Incorrect - On a loss of 1,2 or 3 steam flow indications DFCS will automatically transfer to single element control.

B. Incorrect - On a loss of 1,2 or 3 steam flow indications DFCS will automatically transfer to single element control. Since there was no plant transient (no change in actual feed flow, steam flow or RPV level), DFCS will maintain RPV level as is.

C. Correct - as stated in Step 3.2 of OT-100, If any feedwater flow indication is upscale or any steam line flow indication is downscale, then verify the Feedwater Level Control System is operating in single element control. Since there was no plant transient (no change in actual feed flow, steam flow or RPV level),

DFCS will maintain RPV level as is in single element control.

D. Incorrect - Since there was no plant transient (no change in actual feed flow, steam flow or RPV level), DFCS will maintain RPV level as is in single element control.

1 NRC EXAM Page: 122 of 144 01/31/07

E

--.A-e Question 64 Details Question Type: Multiple Choice Topic: N-ILT-5037-4F-001 Unit 3 is operating at rated power The following conditions exist:

Fire Water System ID: 1189 User ID: N-ILT-5037-4F-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

286000 K4.06 User Text: A User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 I SRO 3.5 Cognitive-Level: Memory

References:

ARC 201 A-3, ARC 201 C-I Justification:

A. Incorrect - The DDFP will auto start at 130 psig fire system pressure.

B. Incorrect -When fire system pressure lowers to 140 psig the Motor Driven Fire Pump (MDFP) will auto start and at 130 psig the Diesel Driven Fire Pump (DDFP) will auto start.

C. Correct -When fire system pressure lowers to 140 psig the Motor Driven Fire Pump (MDFP) will auto start and at 130 psig the Diesel Driven Fire Pump (DDFP) will auto start.

D. Incorrect -When fire system pressure lowers to 140 psig the Motor Driven Fire Pump (MDFP) will auto start and at 130 psig the Diesel Driven Fire Pump (DDFP) will auto start.

NRC EXAM Page: 124 of 144 01I31IO7

Question 65 Details Question Type: Multiple Choice Topic: N-ILT-5002-1Q-001 *A Unit 3 scram condition occurred due to a loss of feedwater transint. *RPV leve System ID: 1303 User ID: N-ILT-5002-1Q-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: I.oo Cross

Reference:

202001K3.07 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.9 / SRO 2.9 Cognitive-Level: High

References:

T-I 00 Bases. ST-0-080-500-2 Justification:

A. Incorrect - Bottom head drain temp is not accurate mostly due RWCU being out of service (isolated at -48" RPV level).

B. Correct - Since RPV level went below -48",

both Recirc pumps tripped and RWCU system isolated. With no core forced circulation or RWCU system flow through the bottom head drain line, bottom head drain line temperature is not accurate.

C. Incorrect - Recirc pumps tripped at -48' RPV level. They are not in service.

D. Incorrect - RWCU is not in service. The system isolated at -48" RPV level.

NRC EXAM Page: 126 of 144 01I31 107

66 ID: N-ILT-4570-12-603 Points: 1.00 An Equipment Operator (EO) accrued the following working hours while working a forced outage.

He does NOT have an authorized "Overtime Guideline Deviation Authorization" form.

Saturday NO HOURS Sunday NO HOURS Monday 06100 - 16:OO Tuesday 06100 - 23:OO Wednesday 06:30 - 22:OO Thursday 07100- 20:OO Friday 06:OO - 22~00 Identify by number which guidelines the EO violated.

1. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

2. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period 3.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period A. 1 and 3 ONLY B. 1 and 2 ONLY C. 1, 2, and 3 D. 2 and 3 ONLY Answer: B NRC EXAM Page: 127 of 144 0 1/31IO7

ID: N-ILT-1504-1-001 Points: 1.00 According to HU-AA-104-101, "Procedure Use and Adherence", when a conflict arises between a standard procedure and a site-specific procedure, which procedure prevails?

A. The standard procedure prevails.

B. The site-specific procedure prevails.

C. The standard procedure prevails except when the site-specific procedure directs actions that ensure compliance with regulatory requirements.

D. The site-specific procedure prevails except when the standard procedure directs actions that ensure compliance with regulatory requirements.

Answer: C Question 67 Details Question Type: Multiple Choice Topic: N-ILT-1504-1-001According to HU-AA-104-101, "Procedure Use and Adherence", when a conflict arises System ID: 1324 User ID: N-ILT-1504-1-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

G2.1.20 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 4.3 / SRO Cognitive-Level: Memory

References:

HU-AA-104-101 Justification:

C. Correct - as stated in HU-AA-104-101, "Whenever a conflict arises between a standard procedure and a site-specific procedure, then the standard procedure shall prevail except when the site-specific procedure directs actions that ensure compliance with regulatory requirements".

NRC EXAM Page: 129 of 144 01/31/07

68 ID: N-ILT-1528-2401 Points: 1.00 Given the following:

0 MO-2-23-057, "HPCI Torus Suction Outboard" was declared INOPERABLE for preventative maintenance.

Following maintenance, operators performed a valve stroke test on MO-2-23-057 using a partial ST-0-023-301-2, "HPCI Pump, Valve, Flow and Unit Coolers Functional and Inservice Test".

0 The OPEN stroke time for the valve exceeded the limiting stroke criteria.

0 The CLOSE stroke time for the valve was acceptable.

Based on the guidance in both ST-0-023-301-2,"HPCI Pump, Valve, Flow and Unit Coolers Functional and Inservice Test", and NOM-P-11.1 "Operability", valve MO-2-23-057:

A. operability status is indeterminate.

B. is OPERABLE since the CLOSE stroke time was ACCEPTABLE.

C. remains INOPERABLE and must be examined to determine the root cause.

D. is OPERABLE if a second OPEN stroke time is in the ACCEPTABLE Range.

Answer: C NRC EXAM Page: 130 of 144 01/31/07

ION ANS 007 NRC R b 'Rev 1 Question 68 Details Question Type: Multiple Choice Topic: N-ILT-1528-2-001 Given the following: A maintenance activity was performed on MO-2-23-057, "HPCI Tor System ID: 1345 User ID: N-ILT-1528-2-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 4 Point Value: 1.oo Cross

Reference:

2.2.24 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.6 / SRO 3.8 Cognitive-Level: Memory

References:

ST-0-023-301-2; NOM-P-11.I Justification:

A. Incorrect - Per NOM-P-11. I there is no "indeterminate'ktatus. The component is either operable or inoperable.

B. Incorrect - the valve's safety function is in the open direction. The open stroke time must meet acceptable times or be declared inoperable.

C. Correct - Per ST-0-023-301-2 Limitation 4.3.2:

Any valve that exceeds its limiting stroke time criteria shall be immediately declared INOPERABLE.

Per NOM-P-11.1, Operability, test failures should be examined to determine the root cause and correct the problem before resumption of testing. Repetitive testing to achieve acceptable test results without identifying the root cause or correction of any problem in a previous test is not acceptable as a means to establish or verify operability. Examples include cycling a valve until acceptable stroke times are achieved.

D. Incorrect - ST-0-023-301-2 gives clear guidance that any valve that exceeds its limiting stroke time criteria shall be immediately declared INOPERABLE.

u NRC EXAM Page: 131 of 144 0 1/31IO7

69 ID:N-ILT-5071L2-002 Points: 1.00 Prior to inserting the TN-68 Spent Fuel Storage cask into the Fuel Pool Cask Pit per procedure SF-220 "Spent Fuel Cask Loading and Transport Operations", Fuel Pool Cooling is.

A. maximized and Fuel Pool level is lowered to between 232' 4" and 232' 5".

B. secured and Fuel Pool level is lowered to between 232' 4" and 232' 5".

C. secured and Fuel Pool level is raised to approximately 232' 6.5" (for Unit 2) or 232' 4.5" (for Unit 3).

D. maximized and Fuel Pool level is raised to approximately 232' 6.5" (for Unit 2) or 232' 4.5" (for Unit 3).

Answer: B Question 69 Details Question Type: Multiple Choice Topic: N-ILT-5071-2-002 Prior to inserting the TN-68 Spent Fuel Storage cask into the Fuel Pool Cask Pit System ID: 1193 User ID: N-ILT-5071-2-002 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

2.2.28 User Text: A User Number I: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.6 / SRO 3.5 Cognitive-Level: Memory

Reference:

PLOT 5071; SF-220 Justification:

A. Incorrect - SF-220 requires that Fuel Pool Cooling System is secured.

B. Correct - Procedure SF-220 requires that Fuel Pool Cooling system is secured and to establish Fuel Pool level between 232' 4" and 232' 5".

C. Incorrect - SF-220 requires Fuel Pool level to be between 232' 4 ' and 232' 5". This is applicable to both units.

D. Incorrect - SF-220 requires that Fuel Pool Cooling system is secured.

NRC EXAM Page: 132 of 144 0 1I31I07

\--- 70 ID:N-ILT-1535-4-001 Points: 1.00 Per OP-AB-300-1003, "BWR Reactivity Maneuver Guidance", a Reactivity Maneuver (ReMA)

Form is required for which of the following activities?

A. Inserting control rods to clear APRM Hi alarms B. Adjusting reactor recirculation flow to maintain full reactor power C. Unplanned insertion of a control rod for operability concerns.

D. Withdrawing control rods during continuation of a reactor startup above 25%

power.

Answer: D NRC EXAM Page: 133 of 144 01/31/07

Question 70 Details Question Type: Multiple Choice Topic: N-ILT-1535-4-001 A Reactivity Maneuver (ReMA) Form is required for which of the following activities System ID: 1194 User ID: N-ILT-15354-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

2.2.34 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: importance: RO 2.8 / SRO 3.2 Cognitive-Level: Memory

References:

OP-AB-300-1003, BWR Reactivity Maneuver Guidance, GP-5 Justification:

A. Incorrect - Inserting control rods to clear APRM Hi alarm is considered a simple reactivity maneuver per OP-AB-300-1003 and a ReMA is not required.

B. incorrect - Routine load changes with reactor recirculation flow is considered a simple reactivity maneuver per OP-AB-300-1003 and a ReMA is not required.

C. Incorrect - Unplanned insertion of a control rod for operability concerns is a simple reactivity maneuver per OP-AB-300-1003 and a ReMA is not required.

D. Correct - Per OP-AB-300-1003, BWR Reactivity Maneuver Guidance continuation of a reactor startup above 25% power is a complex maneuver and requires a ReMA.

NRC EXAM Page: 134 of 144 01131107

\-

72 ID: N-ILT-17304-OO1 Points: 1.00 An Equipment Operator has been assigned to enter the Moisture Separator Area to investigate a steam leak. The following information has been provided.

The Equipment Operator has 3280 TEDE annual Exposure.

Expected dose for investigation of the steam leak is 300 mR.

In accordance with RP-AA-203,"Exposure Control and Authorization", which one of the following describes the action required, if any, to complete the steam leak investigation based on the above conditions?

A. Planned Special Exposure must be obtained.

B. Dose Control Level Extension must be obtained.

C. Emergency Exposure Extension must be obtained.

D. No action required because the Equipment Operator's total exposure will be less than 4000 mR.

Answer: B NRC EXAM Page: 137 of 144 0 1131I07

\---

Question 72 Details Question Type: Multiple Choice Topic: N-ILT-1730-4-001An Equipment Operator has been assigned to enter the Moisture Seperator Area to System ID: 1197 User ID: N-ILT-1730-4-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

2.3.4 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.5 I SRO 3.1 Cognitive-Level: Memory

References:

RP-AA-203, Exposure Control and Authorization Justification:

A. Incorrect - RP-AA-203 required dose extension above 2000 mR TEDE. Dose extensions are granted in 500 mR increments. The current extension is good to 3500 mR. Another extension is required to get to 3580 mR expected exposure. This evolution does not qualify as a Planned Special Exposure or Emergency Exposure Extension.

B. Correct - Per RP-AA-203 C. Incorrect - RP-AA-203 required dose extension above 2000 mR TEDE. Dose extensions are granted in 500 mR increments. The current extension is good to 3500 mR. Another extension is required to get to 3580 mR expected exposure. This evolution does not qualify as a Planned Special Exposure or Emergency Exposure Extension.

D. Incorrect - RP-AA-203 required dose extension above 2000 mR TEDE. Dose extensions are granted in 500 mR increments. The current extension is good to 3500 mR. Another extension is required to get to 3580 mR expected exposure. This evolution does not qualify as a Planned Special Exposure or Emergency Exposure Extension.

NRC EXAM Page: 138 of 144 01131107

.\--- ID:N-1LT-15603-001 Points: 1.00 Fuel failure has resulted in an off-site release to the Main Stack. Unit 2 conditions are as follows:

The reactor was scrammed with all rods inserting

The Main Stack rad release is approaching the ALERT level

Main Steam Line rad is 7,500 mr/hr and slowly rising.

RPV pressure is 940 psig and controlled by EHC.

Per T-100 series procedures, which one of the following actions is REQUIRED to control the radioactive release?

A. Start the Mechanical Vacuum Pump and depressurize to the condenser at < 100 F/hr.

B. Close the Main Steam Isolation Valves and depressurize to the Suppression Pool at < 100 F/hr.

C. Start the Mechanical Vacuum Pump and perform a rapid depressurizationto the condenser regardless of cooldown rates.

D. Close the Main Steam Isolation Valves and perform an Emergency Depressurization.

Answer: B NRC EXAM Page: 139 of 144 01131107

Question 73 Details Question Type: Multiple Choice Topic: N-ILT-1560-3-001 Fuel failure has resulted in an off-site release to the Main Stack. Unit 2 condit System ID: 1198 User ID: N-lLT-1560-3-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

2.3.11 User Text:

User Number I : 0.00 User Number 2: 0.00 Comment: Importance: RO 2.7 / SRO 3.2 Cognitive-Level: High

References:

T-104, Radioactivity Release, T-I 01, RPV Control Justification:

A. Incorrect - MVP will not be started with gross fuel failure and condenser will not be used to depressurize.

B. Correct - T-104 requires MSlVs to be isolated to stop the rad release. Depressurizationwill be performed in accordance with T - I 01 < 100 Flhr.

C. Incorrect - T-I 01 RCP/l2 to rapidly depressurize is not required since rad release is not approaching the GE level (a T-I 04 blowdown limits) and a primary system breach is not in progress.

D. Incorrect - Emergency Blowdown is not required (or permitted) by T-I 04 since rad release is not approaching the GE level and a primary system breach is not in progress.

NRC EXAM Page: 140 of 144 01131107

Question 74 Details Question Type: Multiple Choice Topic: N-ILT-1560-2-004 Unit 3 is operating at 100% power when the following sequence of events occurs:

System ID: 1235 User ID: N-ILT-1560-2-004 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

2.4.2 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.9 / SRO 4.1 Cognitive-Level: High

References:

T-100, T-100 Bases, T-101, T-102, T-I03 Justification:

A. Incorrect - a Group 1 isolation from 100%

power would result in a reactor scram and an RPV Lo Level condition, requiring entry into T-101. As stated in 1-1OO Bases, "T-I OO is entered each time the reactor scrams, provided that an entry condition for T-I 01 does not exist. I' B. Incorrect - none of the given conditions indicate an entry condition for T-I02 ...since HPCl and RCIC have initiated and RHR and Core Spray have not, a High Drywell Pressure condition does not exist.

C. Correct - T-101 would be entered due to an RPV Lo Level condition and T-I 03 would be entered due to the RCIC PUMP ROOM FLOOD alarm.

D. Incorrect -there is no entry condition for T-102.

NRC EXAM Page: 142 of 144 01I31 107

7 NRC RO Rev 75 ID: N-ILT-7540-3-009 Points: 1.00 Unit 2 is operating at 80% power when the following VALID Main Control Room annunciators alarm'

A CONDENSATE PUMP BRK TRIP (203-E2)

REACTOR HI-LO WATER LEVEL (210-H2)

GENERATOR PROTECTION CIRCUIT ENERGIZED (206-Lq)

Which of the following describes the appropriate operator action?

A. Perform GP-4, "Manual Scram" B. Perform GP-9-2, "Fast Reactor Power Reduction" C. Insert ALL GP-9-2 Appendix 1, control rods ONLY.

D. Verify A and B Recirc Pumps runback to 45%.

Answer: A NRC EXAM Page: 143 of 144 01131107

Question 75 Details Question Type: Multiple Choice Topic: N-ILT-1540-3-009 Unit 2 is operating at 90% power when an electrical transient causes several Contro System ID: 1233 User ID: N-ILT-1540-3-009 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

2.4.45 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.3 / SRO 3.6 Cognitive-Level: High

References:

GP-9-2, Fast Reactor Power Reduction; GP-4, Manual Scram; OT-I 00, Reactor Low Level; OT-112, Unexpected/Unexplained Change In Core Flow; OT-113,Loss of Stator Cooling Justification:

.--- - A. Correct - a valid GENERATOR PROTECTION CIRCUIT ENERGIZED annunciator indicates a loss of Stator Cooling. OT-I 13 directs a manual scram IAW GP-4 if a valid loss of Stator Cooling exists and generator load is greater than 7760 amps (-23% reactor power).

B. Incorrect - this action is directed by OT-I00 for a low reactor water level condition, based on availability of makeup capability. This action would be appropriate if it weren't for the loss of Stator Cooling condition.

C. Incorrect - the given conditions indicate a trip of the A Condensate Pump, which results in a Recirc runback to 45%, and requiring entry into OT-I 12. Inserting ALL GP-9-2 rods is required by OT-I 12 only if a recirc pump trip has occurred...none of the given conditions suggest a recirc pump trip has occurred.

C. Incorrect - although this action would be correct in the case of a loss of the A Condensate Pump (which results in a Recirc runback to 45%), it is not the correct initial action due to the loss of Stator Cooling, which requires a reactor scram.

NRC EXAM Page: 144 of 144 01/3 1t07

L/'

ID: N-ILT-5002B-6A-001 L *t Points: 1.00 Given the following:

Unit 2 was initially operating at 100% power 0 A station blackout occurred The following RPV level indications exist:

- Narrow range LI-94A (20C005A) indicates 0 inches Wide range LI-856 (20C005A) indicates -40 inches

. Wide range LR-11OA (20C004C) indicates +20 inches

- Fuel Zone range LR-11OB (2OCOO3-02) indicates +25 inches Using SE-11, Attachment C, determine which statement below is TRUE?

A. Actual RPV level is approximately +20 inches; maintain RPV level per T-I 01.

B. Actual RPV level CANNOT be determined; exit T-101 and enter T-I 16.

C. Actual RPV level is approximately 0 inches; restore and maintain level between

+5 and +35 inches per T-101.

D. Actual RPV level is below 0 inches, but above TAF; restore and maintain level between +5 and +35 inches per T-101.

Answer: D NRC EXAM Page: 1 of 53 01/24/07

Question I betails Question Type: Multiple Choice Topic: N-ILT-5002B-6A-001 Given the following: Unit 2 was initially operating at 100% power System ID: 1360 User ID: N-l LT-5002B-6A-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

295003AA2.02 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO N/A / SRO 4.3 Cognitive-Level: High

References:

SE-11 Attachment C; T-101 THE EXAMINEE WILL NEED SE-11 ATTACHMENT C IN ORDER TO ANSWER THIS QUESTION.

This question salifies the requirement of 10CFR55.43(b)(5)

Justification:

A is incorrect - actual level is approximately -40 inches.

B is incorrect - actual level is approximately -40 inches.

C is incorrect - level is approximately -40 inches.

D is correct - according to SE-11, Attachment C, level indicators LI-94A (narrow range) and LI-85B (wide range) are DC powered and are therefore available during a station blackout. LR-11OA and B are not available. However, the only accurate level indication in this case is LI-85B since LI-94As lowest indication available is 0 inches. Therefore actual level is between 0 inches and TAF (-172") at -40 inches. The correct action to take is to restore RPV level to between +5 and

+35 inches per T-I 01.

NRC EXAM Page: 2 o f 5 3 01124l07

2 " ID: N-ILT-I555-1-015 Points: 1.00 Given the following:

Unit 2 was initially operating at 100% power.

A loss of all off-site power occurred.

Diesel Generator E-I failed to start.

All control rods are fully inserted.

RPV level is -10 inches and steady.

Reactor pressure is 950 psig.

2A DC POWER PANEL LO VOLTAGE (209 C-3) is in alarm.

2A DC Bus voltage at Panel 20C021 (CSR) is 90 VDC.

What actions are required for these conditions?

A. Enter SE-13, "Loss of a 125 or 250 VDC Safety Related Bus" B. Restart the 2A CRD Pump in accordance with SO 3.1.-2,"CRD Hydraulic System Startup with the System Filled and Vented".

C. Place the alternate 2A battery charger in service in accordance with SO 57B.1-2, "125/250 Volt Station Battery Charger Operations".

D. Transfer the 2A battery charger power source from E-I24-T-B to E-I 34-T-B in accordance with A 0 57B.6-2,"Transfer of 125V Battery Charger 2AD003 to Alternate Power and Return to Normal".

Answer: A NRC EXAM Page: 3 o f 5 3 0 1124107

Question 2 betails Question Type: Multiple Choice Topic: N-ILT-1555-1-015 Given the following: *Unit 2 was initially operating at 100% power. *A loss of System ID: 1305 User ID: N-ILT-1555-1-015 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295004AA2.03 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.8 / SRO 2.9 Cognitive-Level: High

References:

ARC 209 C-3, SE-13, A 0 578.6-2 This question satisfies the requirements of 10CFR55.43(b)(5),

Justification:

A. Correct - This is an SE-13 entry condition...the referenced alarm and voltage on a safety-related 125 VDC distribution panel less than 107.45 VDC requires entry into SE-13.

B. Incorrect - Cannot start the 2A CRD Pump due to no power available to the E-12 bus.

C. Incorrect - Both the normal and alternate supply to the battery charger come from the same source.

D. Incorrect - this evolution can only be done when in MODE 4 or 5, as specified in A 0 578.6-2, Prerequisite 2.1.

NRC EXAM Page: 4 o f 5 3 01124107

ANS RO Rev 1 Question 3 Details Question Type: Multiple Choice Topic: N-ILT-5034-4B-007 *Unit 2 is operating at 100% rated power. *The 2A TBCCW pump blocked for maintena System ID: 1306 User ID: N-l LT-5034-4B-007 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295018AA2.04 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.9 / SRO 2.9 Cognitive-Level: High

References:

ON-1 13 This question satisfies the requirements of 10CFR55.43(b)(5).

Justification:

A. Correct - The RBCCW backup does not occur on low pressure. This swap requires that both 480 VAC MCCs are tripped. The CRD pumps are normally supplied by TBCCW.

B. Incorrect - The RBCCW backup does not occur on low pressure. Even if the swap did occur, RBCCW would not supply lsophase Bus Coolers.

C. Incorrect - The RBCCW backup does not occur on low pressure.

D. Incorrect - TBCCW no longer supplies cooling water to the Condensate Filter Demineralizer Hold pumps.

NRC EXAM Page: 6 o f 5 3 01124107

-J

'4 IO: N-ILT-I550-22C-001 Points: 1.00

Unit 3 is operating at 100% power.

An explosion ruptures several Instrument Air lines in the turbine building.

All available air compressors are running.

Instrument Air pressure lowers toward 0 psig.

Control rods begin to drift in.

For the above conditions, per ON-I 19 "Loss of Instrument Air", the crew must enter (1) and use (2) to control RPV pressure and (3) to control RPV level.

A. (1) T-100, "Scram".

(2) SRVs/HPCI.

(3) HPCIIRCIC.

B. (1) T-101, "RPV Control".

(2) SRVslHPCI.

(3) Feedwater.

C. (1) T-I 00, "Scram".

(2) Bypass Valves.

(3) HPCVRCIC.

D. (1) T-101, "RPV Control".

(2) Bypass Valves.

(3) Condensate Pumps.

Answer: A NRC EXAM Page: 7 o f 5 3 01124107

A Question4 Details Question Type: Multiple Choice Topic: N-ILT-1550-22C-001 *Unit 3 is operating at 100%

power. *An explosion ruptures several Instrument System ID: 1308 User ID: N-ILT-1550-22C-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295019AA2.02 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO n/a / SRO 3.7 Cognitive-Level: High This question satisfies the requirements of 10CFR55.43(b)(5).

References:

ON-I 19 Justification:

A. Correct - Outboard MSlVs will go closed on a loss of air, therefore no steam for feed pumps or use of the main condenser for decay heat.

Condensate is available for injection however it is not preferred due to AO-9091, C RFP bypass failed open on loss of air and increasing RPV level in an uncontrolled manner. HPCVRCIC are totally unaffected by loss of air.

B. Incorrect - CRD flow control valves fail closed on a loss of air.

C. Incorrect - Condenser is not available for pressure control due to MSlVs going closed on loss of air.

D. Incorrect - Condenser is not available due to MSlVs going closed on loss of air.

u-.

NRC EXAM Page: 8 of 53 01/24/07

Question 5 Details Question Type: Multiple Choice Topic: N-ILT-I800-2-004 During Refueling Operations RPV water level is required to be System ID: 1307 User ID: N-l LT-1800-2-004 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

29502362.2.25 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO / SRO 3.7 Cognitive-Level: Memory This question satisfies the requirementsof 10CFR55.43(b)(2).

References:

Tech Spec 3.9.6 Justification:

A. Incorrect - Correct basis, incorrect applicability.

Also applicable during handling of control rods.

B. Correct - (1) This is the basis as stated in Tech Spec 3.9.6 Bases. (2) This is consistent with the applicability statement of Tech Spec LCO 3.9.6.

C. Incorrect - Incorrect basis, incorrect applicability.

D. Incorrect - incorrect basis, correct applicability.

NRC EXAM Page: 10 of 53 0 1124107

Question 6 Details Question Type: Multiple Choice Topic: N-ILT-1550-3-005 Consider the following timeline:

1O:lO - Unit 2 Turbine Building 116' Elev. fire a System ID: 1368 User ID: N-ILT-1550-3-005 Status: Active Always select on test: No Authorized for practice: No DifficuIty : 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

600000 G2.4.30 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.2 / SRO 3.6 This question satisfies the requirements of 10CFR55.43(b)(5).

References:

ON-114: FF-01 Justification:

A. Incorrect - Time is incorrectly based on 10 minutes after the fire alarm. GP-4 is only directed per ON-I 14 if the fire jeopardizes normal plant shutdown OR ECCS.

B. Incorrect - Time is incorrectly based on 10 minutes after the actual fire report or 15 minutes after the fire alarm (this time actually corresponds to when an Emergency Classification is made per ON-I 14). The Floor Supv. role by FF-01 is not to relieve the Incident Commander, but to coordinate between the IC and the MCR.

C. Correct - Time is correctly based on 20 minutes after receipt of the fire alarm. ON-I 14 states that IF the fire brigade cannot extinguish the fire AND off-site assistance is required, THEN commence a controlled plant shutdown using GP-3.

D. Incorrect - Time is incorrectly based on 20 minutes after the report of an actual fire. RPV condensing chamber backfill is only isolated with a Reactor Building fire.

NRC EXAM Page: 12 of 53 01/24/07

Question f Details Question Type: Multiple Choice Topic: N-ILT-2101-1-011 *Unit 2 is operating at 80% reactor power. *An electrical problem has resulted in System ID: 1310 User ID: N-ILT-210 1-1 -0 11 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295031'32.4.4 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO nla I SRO 4.3 Cognitive-Level: High This question satisfies the requirements of 10CFR55.43(b)(5).

References:

T-100 Bases, T-101 Justification:

A. Incorrect - T-100, "Scram", is not entered. T-101 is entered for low RPV level @ -50 inches.

B. Correct - An ATWS is in progress since it cannot be determined where control rods are positioned. T-101 is entered due to RPV level

@ -50 inches.

C. Incorrect - An ATWS is in progress, since it cannot be determined where control are positioned.

D. Incorrect - An ATWS is in progress. T-100, "Scram" should not be entered.

NRC EXAM Page: 14 of 53 01124107

00'0

, 00'0

Comment: Importance: RO NIA I SRO 3.9 Cognitive-Level: High This question satisfies the requirements of 10CFR55,43(b)(5)

References:

OT-102; OT-I 10; T-101 THE EXAMINEE WILL NEED OT-I 10 FIGURE 1 IN ORDER TO ANSWER THIS QUESTION.

Justification:

A is incorrect - Per OT-I 10 Figure 1 an indicated level of +90 inches indicates that actual RPV level may be at or above the main steam lines. OT-1 I O directs closing the MSlVs if RPV level cannot be maintain below the bottom of the MSlVs (+I08 inches), thereby taking away the use of BPVs. In addition, while OT-102 does direct maintaining reactor pressure below 1053 psig, since the reactor is scrammed, OT-102 is no longer applicable. OT-I 10 is executed concurrently with T-I 01 "RPV Control".

B is incorrect Per OT-I 10 Figure 1 an indicated level of +90 inches indicates that actual RPV level may be at or above the main steam lines. OT-I 10 directs closing the MSlVs if RPV level cannot be maintain below the bottom of the MSlVs (+I08 inches). In addition, while OT-I 02 does direct maintaining reactor pressure below 1053 psig, since the reactor is scrammed, OT-102 is no longer applicable. OT-I 10 is executed concurrently with T-I01 "RPV Control".

C is correct -when RPV pressure reaches 1050 psig, OT-I 10, which is executed concurrently with T-I 0 1,"RPV Control", directs manual SRV operation using a single SRV (if possible) and prolonged SRV opening.

D is incorrect - OT-I 10 directs prolonged SRV opening using a single SRV (or as few as possible) in order to minimize SRV tailpipe loading and the number of SRVs that are effected by higher than normal loads.

NRC EXAM Page: 17 of 53 01124107

TION AN 200'7NRC SRO Rev I u'

9 ID:N-ILT-5007-8-007 Points: 1.00 Given the following conditions:

Unit 2 is at 100% power.

The HPCl System is in service per ST-0-023-301-2, "HPCI Pump, Valve, Flow and Unit Cooler Functional and In-Service Test".

Torus Cooling is in service per SO 10.1.D-2.

Torus bulk averaae temperature on SPOTMOS TIS-2-2-71A reaches 96°F during testing and the Control Room Supervisor entered T-102, "Primary Containment Control".

The Reactor Operator who is recording Torus temperature per ST-0-023-301-2 observes that local Torus water temperature at the Torus Bay location where the HPCl turbine is exhausting is at 106OF.

What action(s), if any, is/are required?

A. Verify Torus water average temperature I110°F once per hour ONLY.

B. Immediately suspend all HPCl testing since it is adding heat to the Torus.

C. Verify Torus water average temperature 5 110°F once per hour AND Restore Torus average temperature to 595OF within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D. No additional action required. Torus water temperature will continue to be monitored every 5 minutes while HPCl remains in service.

Answer: D NRC EXAM Page: 18 of 53 01124107

Question 9 Details Question Type: Multiple Choice Topic: N-ILT-5007-8-007 Given the following conditons: *Unit 2 is at 100% power. *ST-0-023-301-2, HPCl System ID: 1312 User ID: N-ILT-5007-8-007 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

295013AA2.02 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.2 / SRO 3.5 Cognitive-Level: High This question satisfies the requirements of 10CFR55.43 (b)(2).

References:

ST-0-023-301, TS 3.6.2.1 Justification:

A. Incorrect - This addresses a required action of 3.6.2.1 .A.1 (> 95OF average Torus temperature) which is NOT applicable due to testing in progress that is adding heat to the Torus.

B. Incorrect - This action is driven by TS 3.6.2.1.C for Torus temperature > 105OF (average temperature). Average Torus temperature is presently 96OF.

C. Incorrect - This addresses required actions of 3.6.2.1.A.l and A.2 (> 95OF average Torus temperature) which is NOT applicable due to testing in progress that is adding heat to the Torus.

D. Correct - Tech Spec 3.6.2.1 for Torus temperature is concerned with only average water temperature, not local readings. No action is required by TS 3.6.2.1 since SPOTMOS RIS-2-2-71A is reading an average of 96OF with testing going on that adds heat to the Torus. The next action level would be at a Torus temperature of 105OF at which all testing would be suspended per T.S. 3.6.2.1.C and ST-0-023-301-2.

NRC EXAM Page: 19 of 53 01I24107

10 ID:N-ILT-1560-3405 Points: 1.00

Unit 3 is at 70% power.

Annunciator 323 (E-5) A RHR PUMP ROOM FLOOD is received.

Two minutes later annunciator 326 (A-4) TORUS WATER LEVEL OUT OF NORMAL RANGE is received.

Torus level is 14.2 feet and lowering slowly.

The Equipment Operator sent to investigate the alarms reports back that he cannot get into the ' A RHR room from the 116' elevation.

Which of the following best describes the cause of the above conditions and what are the required procedure actions?

A.

RHR Pump A suction line break ONLY.

Monitor Torus level.

Declare an Alert.

B.

RHR Pump A andlor RHR Pump C suction line break.

Immediately perform a manual scram using procedure GP-4 AND enter T-I 01, "RPV Control".

Declare an Alert.

C.

RHR Pump A suction line break ONLY.

Enter T-102,"Primary Containment Control".

Restore Torus water level to normal, or if not possible, commence a GP-3 shutdown.

D.

RHR Pump A and/or RHR Pump C suction line break.

Restore Torus water level to normal using RClC minimum flow line, or if not possible, commence a GP-3 shutdown.

Enter Tech Spec 3.6.2.2 for Suppression Pool Water Level.

Answer: C NRC EXAM Page: 20 of 53 01/24/07

00'0 00'0

,/-,

Comment: Importance: RO 3.4 I SRO 3.8 Cognitive-Level: High This question satisfies the requirementsof 10CFR55.43(b)(5).

References:

T-102, T-103, TS 3.6 Justification:

A. Incorrect - All actions are correct with the exception of declaring an Alert. There is no EAL resulting in an Alert until Torus level reaches the unsafe side of the Heat Capacity Temperature Limit (HCTL) curve.

B. Incorrect - The break is on the A RHR pump suction, not the C RHR pump suction. The A and C RHR Rooms are separated at lower elevations by a water tight door, preventing cross flooding from one room to the other.

Performing a GP-4 scram and entering T-I 01 would not be required until it was determined that Torus level could not be maintained above 12.5 feet. There is no EAL resulting in an Alert until Torus level reaches the unsafe side of the Heat Capacity Temperature Limit (HCTL) curve.

C. Correct - The break is associated with the A RHR pump suction piping. T-I02 entry is applicable once Torus water level is < 14.5 feet, and directs to restore Torus water level to normal, or if not possible, commence a GP-3 shutdown (step TIL-3).

D. Incorrect - The break is associated with the A RHR pump suction piping, not the C RHR pump suction. The A and C RHR Rooms are separated at lower elevations by a water tight door, preventing cross flooding from one room to the other. The RClC System would not be a system used to restore Torus level. T-I02 step T/L-5 directs using either HPCI, Condensate transfer, or HPSW systems.

NRC EXAM Page: 22 of 53 01/24/07

L/

11 ID:N-lLTS023-6D-001 Points: 1.00 Unit 3 conditions are as follows:

A scram occurred due to a primary system leak into the drywell.

HPCI is being used to maintain RPV level at approximately +10 inches.

A large leak occurs on the Unit 3 CST and present level is 4' 6" and lowering.

The PRO notifies the Control Room Supervisor that the HPCl System valve lineup is unchanged.

Based on the above conditions, what actions are required, if any?

A. CST level is adequate to support continued HPCI System operation. The PRO will continue to monitor CST level.

B. CST level is to be recovered using SO 27.1.A, "Condensate Transfer and Storage System Startup and Normal Operation".

C. HPCI System suction is to be transferred manually using SO 23.7.8-3, "Transfer of HPCl Suction From CST to Torus".

D. The HPCI System is to be isolated and RCIC is to be placed into service for RPV level control using RRC 13.1-3, "RCIC System Operation During a Plant Event."

Answer: C NRC EXAM Page: 23 of 53 01/24/07

NS Rev 1 Question I 1 Details Question Type: Multiple Choice Topic: N-ILT-5023-6D-001 Unit 3 conditions are as follows: A scram occurred due to a primary system leak in System ID: 1346 User ID: N-ILT-5023-6D-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 4 Point Value: 1.oo Cross

Reference:

206000A2.09 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.5 / SRO 3.7 Cognitive-Level: High This question satisfies the requirements of 10CFR55,43(b)(5).

References:

ARC 321 C-3; SO 23.7.B-3 Justification:

A. Incorrect - Action to swap HPCl suction to the Torus is given in ARC 321 C-3.

B. Incorrect - Condensate transfer system takes suction from the CST and does not have the capability to normally makeup to the CST.

C. Correct - ARC 321 C-3 provides the guidance that on Low-Low CST level the operator is to verify that HPCl suction valves automatically swap from the CST to the Torus. If no automatic function occurs, the operator is to perform SO 23.7.B-3 to manually swap suction to the Torus.

D. Incorrect - RClC also takes normal suction from the CST and would be affected by the Low-Low CST level condition. With HPCl already in service and capable of maintaining RPV level, there is no need to place RClC in service at this time.

'=-J NRC EXAM Page: 24 of 53 01124107

'W' 1'2 ID: N-ILT-1540-5405 Points: 1.N)

Unit 2 is operating at 100% power when a fuel failure occurs.

e Main steam line radiation levels on Panel 20C010 are reading 6 Rlhr and rising quickly Based on the above condition what is the effect on the plant and what actions need to be taken?

A. An automatic scram should have occurred at 5 Rlhr.

Perform GP-4 "Manual Reactor Scram".

Declare an Unusual Event.

B. A Group I isolation will occur at approximately 15 Rlhr Scram and enter T-I 00, "Scram".

Declare an Unusual Event.

C. An automatic scram will occur at approximately 10 R/hr Enter OT-103, Main Steam Line High Radiation".

Perform GP-4, "Manual Reactor Scram".

D. An automatic scram should have occurred at 5 R/hr.

Perform GP-4, "Manual Reactor Scram".

Close the MSlVs in accordance with OT-103,"Main Steam Line High Radiation".

Answer: C NRC EXAM Page: 25 of 53 01/24/07

Question 12 Details Question Type: Multiple Choice Topic: N-ILT-1540-5-005 Unit 2 was operating at 100% power when a gross fuel failure occurred. Main steam System ID: 1314 User ID: N-ILT-1540-5-005 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

2 12000A2.17 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO n/a / SRO 4.2 Cognitive-Level: High This question satisfies the requirements of 10CFR55.43(b)(5).

References:

OT-I 03. EP-AA-1007 Justification:

A. incorrect - MSL radiation levels have not yet risen to the scram setpoint of IOxNFPB, which is -10,000 mR/hr. At this time it would be prudent to perform GP-4 and manually scram.

However, IOxNFPB, which is -10,000 mR/hr is also the threshold value for declaring an Unusual Event IAW EAL RU3.

8. Incorrect - MSL radiation levels for the Group I isolation setpoint is IOxNFPB, which is -10,000 mR/hr. This is also the threshold value for declaring an Unusual Event IAW EAL RU3.

C. Correct -When MSL radiation levels reach (or are expected to each) 8000mR/hr, OT-103 directs a manual scram IAW GP-4.

D. incorrect - OT-103 does not require closing the MSlVs and in fact directs actions to prevent the Group I isolation and loss of the main condenser as a heat sink ... per OT-103 bases:

a GP-4 scram at 8000 mR/hr is directed to minimize the pressure transient caused by the MSIV closure that will occur if radiation levels continue to rise; in addition, performing the GP-4 scram may cause MSL radiation levels to remain below the Group I isolation setpoint, thereby maintaining the main condenser as a heat sink.

NRC EXAM Page: 26 of 53 01124107

Question 13 Details Question Type: Multiple Choice Topic: N-ILT-5001G-8-003 *Unit 2 has been operating at 100% power. *For the past 5 days the 'G' SRV has System ID: 1315 User ID: N-ILT-5001G-8-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: I.oo Cross

Reference:

218000G2.1.33 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO n/a / SRO 4.0 Cognitive-Level: High This question satisfies the requirements of 10CFR55.43(b)(2).

References:

Tech Spec 3.5.1, Tech Spec 3.4.3 Justification:

A. Correct - Leaking bellows only affects the non-ADS safety function. T.S. 3.4.3 would be referenced for this condition. T.S. 3.4.3 requires 11 total (SRV & SVs) to be operable.

Even with the G & D SRVs inoperable T.S.

3.4.3 is still satisfied. No action required.

B. Incorrect - This action would be driven by T.S.

3.5.1.G. This Spec. is not applicable since the ADS function of the 'G' SRV is still operable.

Only the SRV function of the 'G' SRV is affected with the bellows alarm in.

C. Incorrect - This action would be driven by T.S.

3.4.3.A if a 3rd SRV were inoperable.

D. Incorrect - This action would be driven by T.S.

3.5.1.Hif two or more ADS valves were inoperable.

Page: 28 of 53 01124107 NRC EXAM

b 14 ID: N-ILT-5006-8-006 irits: I.

0 Unit 2 is in MODE 1 at 20% power.

0 It has been identified that the Main Turbine and the Reactor Feed Pump Turbine (RFPT) high RPV water level trips from the Digital Feedwater Control System (DFCS) computer DCC-X are set at +51 inches.

What actions, if any, are required for the above condition and why?

A. Place the channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ONLY,based on one RPV high water level trip channel being inoperable.

B. Restore DFCS RPV high water level trip capability within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND place the channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , based on RPV high water level trip capability NOT being maintained.

C. No actions required. The wide range signals which trip HPCl and RCIC provide adequate trip capability for the Main Turbine and the RFPTs.

D. No actions required. The DFCS high RPV water level trips for the Main Turbine and the RFPTs are not required to be operable at this time.

Answer: D NRC EXAM Page: 29 of 53 01124107

Questis 14 Details Question Type: Multiple Choice Topic: N-ILT-5006-8-006 Unit 2 is in MODE 1 at 20% power. It has been identified that the Main Turbine and System ID: 1361 User ID: N-l LT-5006-8-006 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

259002 G2.2.22 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 3.4 / SRO 4.1 Cognitive-Level: High

References:

Tech Spec 3.3.2.2 and Bases This question satisfies the requirements of 10CFR55.43(b)(2).

Justification:

A. Incorrect. No actions are required due to RTP being

<25%. This would be the required action per Spec.

3.3.2.2.A if power were 225% and one or more DFCS high water level trip channels were inoperable.

B. Incorrect. For the conditions given, this would be the correct Tech. Spec. action to enter per 3.3.2.2.B if power were L 25%. No actions are required due to RTP being <25%.

C. Incorrect. While the RPV level inputs from RClC would be sufficient to still trip the Main Turbine, and the inputs from HPCl would be sufficient to still trip the RFPTs, Tech. Spec. 3.3.2.2 requires the 2 channels per trip system from the DFCS to be operable. No actions are required due to RTP being <25%.

D. Correct. While the trips out of the DCC-X computer are inoperable (> +49')),there are no actions required due to RTP being <25%. Spec. 3.3.2.2 applicability requires 2 channels per trip system to be operable L 25% power to ensure that the fuel clad integrity Safety Limit and the cladding 1% plastic strain limit is not violated during the feedwater controller failure, max.

demand event.

NRC EXAM Page: 30 of 53 01124107

L O/PZ/ LO E S P LE :a6ed W W 3 3tlN ION ANSWER KEY Rev Question 15 Details Question Type: Multiple Choice Topic: N-ILT-5057-8-002 *Unit 2 is at 100% power. *Battery charger 2AD003 has been placed in the equalize System ID: 1317 User ID: N-lLT-5057-8-002 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

263000A2.02 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO n/a / SRO 2.9 Cognitive-Level: High This question satisfies the requirementsof IOCFR55.43{b)(2).

References:

TRM 3.14.10 Justification:

A. Incorrect - Actions for Battery Room Ventilation exhaust air flow detector not being functional are required by TRM 3.14.10.

B. Incorrect - This answer does not address all required actions of TRM 3.14.10.A and the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time frame is not correct.

Should be 14 days vs. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Moisture buildup is not an issue.

C. Incorrect - 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months completion time is not correct. Should be 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D. Correct - These actions satisfy the requirements of TRM 3.14.10.A.

NRC EXAM Page: 32 of 53 01124107

P.

Question 16 Details Question Type: Multiple Choice Topic: N-ILT-5002-6G-003Given the following: *Unit 2 is operating at 100% power. *The Total Feed Flow System ID: 1318 User ID: N-lLT-5002-6G-003 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 4 Point Value: I.oo Cross

Reference:

202002A2.07 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO n/a / SRO 3.3 Cognitive-Level: High This question satisfies the requirements of 10CFR55.43(b)(5).

References:

ARC 211 B-3, OT-I 12 Justification:

A. Incorrect - The given conditions indicate the OPRM System is inoperable, requiring performance of A 0 60A. 1-2. Performing a recirc. system runback signal reset is not an initial priority action.

B. Incorrect - < 20% total feedwater flow causes a Recirc runback to 30%.

C. -

Correct < 20% total feedwater flow causes a Recirc runback to 30%. This would result in the OPRM trip output to RPS to be enabled when recirc flow goes below -60 percent while APRM STP is above 30 percent. The OPRM TRIP ENABLED annunciator would be expected to alarm during/following the runback.

If this annunciator does not alarm, the OPRM System would be assumed to be inoperable, in which case OT-I 12 directs performing A 0 60A.1.-2.

D. Incorrect - < 20% total feedwater flow causes a Recirc runback to 30%.

NRC EXAM Page: 34 of 53 01/24/07

3 ANSWER "u'

Question 17 Details '

Question Type: Multiple Choice Topic: N-ILT-5001B-6A-001 A Unit 2 startup is in progress with the following plant conditions: *Reactor System ID: 1319 User ID: N-ILT-5001B-6A-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

245000A2.05 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO n/a / SRO 3.8 Cognitive-Level: High This question satisfies the requirements of 10CFR55.43(b)(5).

References:

GP-2, ARC 206 B-I , TS Bases 3.3.1.1 Justification:

A. Incorrect - The reactor does not automatically scram.

B. Correct - If the PLU circuit energizes, a generator lockout and turbine trip will occur.

Since reactor power is < 29.5% RTP (turbine 1st stage pressure is < 138.4 psig), a reactor scram will not occur as a result of the TSVlTCV closure. The turbine bypass valves will rapidly open, preventing a scram from high reactor pressureheutron flux. The end result will be the reactor at 25% power with the turbine-generator off-line. Per HU-AA-104-101, "Procedure Use and Adherence", steps 4.1.5 and 4.1.7, halting progress on the startup per GP-2 would be required due to conditions changing which would necessitate re-evaluation of the procedure against the new plant conditions.

C. Incorrect - The reactor does not automatically scram.

D. Incorrect - The PLU circuit will produce a generator IockouVturbinetrip.

NRC EXAM Page: 36 of 53 01/24/07

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19 ID: N-ILT-18554-002 Points: 1.00 Which one of the following identifies Work Execution Centerwork Control Center Supervisor (WECS) staffing requirements per OP-AA-101-111 and OP-PB-101-11I?

A. The WECS may be credited as Shift Technical Advisor and Incident Assessor simultaneously.

B. The WECS may be credited as Incident Assessor and NRC Communicator simultaneously.

C. If the WECS is credited as Shift Technical Advisor then the Incident Assessor function is NOT required.

D. If the WECS is credited as Incident Assessor then the Shift Technical Advisor function is NOT required.

Answer: C NRC EXAM Page: 39 of 53 01/24/07

.Question 19 Details Question Type: Multiple Choice Topic: N-ILT-1855-4-002 Which one of the following identifies Work Execution CenterNVork Control Center Sup System ID: 1355 User ID: N-ILT-18554-002 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 4 Point Value: 1.oo Cross

Reference:

G2.1.4 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: R 2.3 I SRO 3.4 Cognitive-Level: Memory

References:

OP-AA-101-111, OP-PB-101-111 This question satisfies 10CFR55,43(b)(2).

Justification:

A. Incorrect - WCS cannot be both STA and IA per OP-PB-101-111.

B. Incorrect - WCS cannot be both the IA and the NRC Communicator per OP-PB-101-111.

C. Correct - If WCS is the STA then IA function is NOT required per OP-AA-I 01-1 11. This is also inferred from OP-PB-101-111 step 4.5.3 which states that if the Shift Manager or Control Room Supv. is the STA, than another SRO MUST be the Incident Assessor.

Therefore, if the WECS is assigned as the STA, an Incident Assessor is NOT REQUIRED.

D. Incorrect - If WCS is the IA, they support the STA function, the STA is still required.

NRC EXAM Page: 40 of 53 01124107

20 ' ID:N-ILT-1526-3-001 Points: 1.00 Given the following conditions:

The Control Room Supervisor (CRS) has deleuated reactivity oversight of Unit 3 to a fully qualified Senior Reactor Operator (SRO) during a GP-2 startup.

This has been logged in the Unified Control Room Log.

During the Unit 3 startup a problem requires entry into T-103, "Secondary Containment Control".

Unit 2 is operating at 75% power during this time.

Which of the following delineates the responsibility for command and control authority on each of the two Units for these conditions?

A. In accordance with OP-AA-101-111,"Roles and Responsibilities of On-Shift Personnel", the CRS shall retain command and control over both Units at all times.

B. In accordance with OP-AA-103-102, "Watchstanding Practices", the Unit 3 reactivity SRO retains command control over Unit 3 until an emergency no longer exists. The CRS retains command and control over Unit 2.

C. In accordance with OP-AA-101-111,"Roles and Responsibilitiesof On-Shift Personnel", the Shift Manager shall assume command and control over both Units upon his arrival in the Main Control Room.

'c-' D. In accordance with OP-AA-103-102, "Watchstanding Practices", the Unit 3 reactivity SRO immediately transfers Unit 3 command and control to the Shift Manager and provides support and backup to the CRS on both Units.

Answer: A NRC EXAM Page: 41 of 53 01/24/07

Question 20 Details Question Type: Multiple Choice Topic: N-ILT-1526-3-001 Given the following conditions: *The Control Room Supervisor (CRS) has delegated System ID: 1325 User ID: N-ILT-1526-3-001 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

G2.1.6 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.1 / SRO 4.3 Cognitive-Level: Memory This question satisfies the requirements of 10CFR.55.43(b)(5).

References:

OP-AA-I 01-1 11 Justification:

A. Correct - OP-AA-101-111, "Roles and Responsibilities of On-Shift Personnel", section 4.2 states "During a transient, the Unit Supervisor (CRS) will immediately position himself as the control authority for the unit, acknowledging immediate operator actions being verbalized and taken by the Reactor Operators. After assessing the situation, the Unit Supervisor (CRS) will direct subsequent operator actions in accordance with applicable procedures until conditions are stable and a transient condition no longer exists (specifically step 4.2.10).

B. Incorrect - The qualified SRO never officially turned over to the Unit Supervisor (CRS).

C. Incorrect - It is the Unit Supervisor (CRS) who maintains command and control per OP-AA-101-111, not the Shift Manager.

D. Incorrect - Neither the qualified SRO or the Shift Manager obtained command and control.

The Unit Supervisor (CRS) always had command and control.

NRC EXAM Page: 42 of 53 01/24/07

21 ID: N-ILT-501040-004 Points: 1.00 Unit 2 is shutdown with all control rods fully inserted.

RPV level is +25 inches.

The 2A RHR Pump is running in Shutdown Cooling at 9,000 gpm flow per SO 10.l.B-2 "RHR System Shutdown Cooling Mode Manual Start".

Maintenance requests to locally set the open and closed limit switches on MO 2-IO-16A"RHR Pump Min. Flow Valve".

This action will require the M O 2-10-16A to be taken off of its closed seat.

Authorization to perform the work (1) be granted based on (2)

A. ( I ) CAN (2) no plant impact if the 2A RHR Pump ONLY is first secured per SO 10.l.B-2.

B. (1) CAN (2) no plant impact if the 2A RHR Pump is secured and the MO-2-10-25A "Inboard Discharge Valve" is closed first per SO IO.1.B-2.

C. (1) CANNOT (2) a PClS Group I I Shutdown Cooling isolation would occur requiring entry into ON-I 25 "Loss or Unavailabilityof Shutdown Cooling".

D. (I) CANNOT (2) the 2A RHR Pump would trip on overcurrent due to excessive pump flow (pump runout) requiring entry into ON-125 "Loss or Unavailabilityof Shutdown Cooling".

Answer: C NRC EXAM Page: 43 of 53 01124107

Question 21 Details Question Type: Multiple Choice Topic: N-ILT-5010-40-004 Unit 2 is shutdown with the 2A RHR Pump running in Shutdown Cooling at 9,000 gpm f

System ID: 1362 User ID: N-ILT-5010-40-004 Status: Active Always select on test: No Authorized for practice: No Difficulty: 2.50 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

205000G2.2.18 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.3 / SRO 3.6 Cognitive-Level: Memory This question satisfies the requirements of 10CFR55.43(b)(5).

References:

SO 10.1.8-2, ON-125 Justification:

A. Incorrect - The work cannot occur due to reactor water being diverted to the Torus if the minimum flow valve MO-16A is opened.

B. Incorrect - The work cannot occur due to reactor water being diverted to the Torus if the minimum flow valve MO-16A is opened. Also, to avoid diverting flow to the Torus either the SDC suction MO-17, MO-18, or MO-15A would need to be closed.

C. Correct - The work cannot occur because reactor water would lower due to being diverted to the Torus if minimum flow valve MO-16A is opened. To prevent this from occurring, the minimum flow valve for the RHR pump in shutdown cooling is procedurally controlled closed with its feed removed during shutdown cooling operation. ON-125 would have to be entered once the PClS Group II isolation occurred since shutdown cooling would become unavailable.

D. Incorrect - Even with the minimum flow valve fully open during pump operation the RHR pump total flow would not exceed pump runout flow of >12, 500 gpm.

NRC EXAM Page: 44 of 53 01/24/07

/---..

EXAMINATION ANSWER KEY S I Question 23 Details Question Type: Multiple Choice Topic: N-ILT-1770-3-004 The Main Control Room has been abandoned due to a fire. Equipment Operators are goi System ID: 1356 User ID: N-ILT-I 770-3-004 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.oo Cross

Reference:

G2.3.1 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO 2.6 I SRO 3.0 Cognitive-Level: Memory

References:

RP-AA-460: RP-PB-460-1001 This question satisfies the requirement of 10CFR55.42(b)(4).

Justification:

A. Incorrect- The level is incorrect. The area is a Level 2 (?I 5R/hr) which requires authorization from the RP Manager for issuing the key.

B. Incorrect - The level is incorrect, and the Plant Manager's authorization is NOT required.

C. Correct - Per RP-AA-460-1001, Level 2 LHRA is an area with dose rates ? 15Rlhr. The RP Manager must provide authorization for this entry.

D. Incorrect -While the level is correct, the RP Manager must provide authorization for this entry.

NRC EXAM Page: 48 of 53 01/24/07

Question Type: Multiple Choice Topic: N-ILT-2117-5A-006 During an ATWS, automatic initiation of the Automatic Depressurization System System ID: 1329 User ID: N-ILT-2117-5A-006 Status: Active Always select on test: No Authorized for practice: No Difficulty: 3.00 Time to Complete: 2 Point Value: 1.oo Cross

Reference:

G2.4.22 User Text:

User Number 1: 0.00 User Number 2: 0.00 Comment: Importance: RO nla I SRO 4.0 Cognitive-Level: Memory This question satisfies the requirements of 1OCF55.43(b)(5).

References:

T-I 17 Bases Justification:

A. Incorrect - During an ATWS Torus temperature may exceed 11O°F before boron injection anyway due to SRV operation...this is not the reason for inhibiting ADS.

B. Incorrect - Depressurizationdue to ADS initiation must also be accompanied by elevated Drywell temperature for this to occur...this is the reason for inhibiting ADS.

C. Incorrect - ADS initiation would not cause large irregular neutron flux oscillations...it would cause a rapid reduction in reactor power due to voids.

D. Correct - For the given conditions an ATWS exists due to control rods remaining out beyond position 02. From T-I 17 Bases: ADS initiation would complicate efforts to maintain RPV level within required level ranges.

FURTHER, rapid and uncontrolled injection of large volumes of relatively cold, un-borated water from low pressure injection systems may occur. Wlth the reactor either critical or shutdown on boron alone, the positive reactivity addition due to boron dilution and temperature reduction may result in a reactor power excursion large enough to cause substantial fuel damage. ADS is inhibited to prevent this from happening.

NRC EXAM Page: 50 of 53 01124107

25 ID: N-ILT-1529-1Ha01 Points: 1.00 It has been verified that the 2D Core Spray Pump Room flood detection level switch LS-2920D does not function and will not bring in annunciator 226 (D-5) D CORE SPRAY PUMP ROOM FLOOD.

Which of the following describes the actions to be taken for the above condition?

A. Place an equipment deficiency taglsticker on Annunciator 226 (D-5) and designate the annunciator for "Non-Preferred Use" per OP-AA-108-105, "Equipment Deficiency Identification and Documentation".

B. Place an equipment status taglsticker on Annunciator 226 (D-5) and utilize an Abnormal Component Position Sheet (ACPS) to control the abnormal condition per OP-AA-108-101,"Control of Equipment and System Status".

C. Place an equipment deficiency tagkticker on the associated Alarm Response Card, evaluate the impact on implementing Emergency Operating Procedures, and identify any compensatory actions or additional monitoring per OP-AA-108-105, "Equipment Deficiency Identification and Documentation".

D. Place an equipment status taglsticker on the associated Alarm Response Card, document the deficiency in the Equipment Status Tag Log, and place the annunciator in MANUAL per OP-AA-108-101,"Control of Equipment and System Status".

Answer: C

.W' NRC EXAM Page: 51 of 53 01I24107

00'0 00'0

Comment: Importance: RO 2.4 / SRO 2.8 Cognitive-Level: Memory References : OP-AA-108-105 Equipment Deficiency Identification and Documentation This question satisfies the requirements of 10CFR55.43(b)(5).

Justification:

A. Incorrect - Peach Bottom present practicelmanagement expectation is to place a deficiency sticker on the Alarm Response Card (ARC) associated with the annunciator. Also, use of an Equipment Status Tag (EST) is for identifying TEMPORARY abnormal equipment positioning. For this example, nothing was placed in an abnormal position in response to the inoperable annunciator.

Also, "Non-Preferred Use" is for degraded equipment issues. The Core Spray Room flood alarm system is completely inoperable, not degraded.

B. Use of an Equipment Status Tag (EST) and the Abnormal Component Position Sheet (ACPS) is for

. . identifying TEMPORARY abnormal equipment positioning. For this example, nothing was placed in an abnormal position in response to the inoperable annunciator condition.

C. Correct - OP-AA-108-105, "Equipment Deficiency Identification and Documentation" directs several actions for this condition including evaluating the impact on implementing Emergency Operating Procedures, identifying any compensatory actions or additional monitoring, and placement of an equipment deficiency taglsticker for the deficient item. Peach Bottom present practicelmanagementexpectation is to place a deficiency sticker on the Alarm Response Card (ARC) associated with the annunciator.

D. Peach Bottom present practicelmanagement expectation is to place a deficiency sticker on the Alarm Response Card (ARC) associated with the annunciator.

Also, use of an Equipment Status Tag (EST) and the Abnormal Component Position Sheet (ACPS) is for identifying TEMPORARY abnormal equipment positioning. For this example, nothing was placed in an abnormal position in response to the inoperable annunciator condition. There is no need to place the annunciator in MANUAL and it is not directed by OP-AA-108-101.

NRC EXAM Page: 53 of 53 01124107

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