Text

2014 Prairie Island Nuclear Generating Plant Initial License Examination Administered Written Examination - Reactor Operator
	ML15126A554
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Site:	Prairie Island
Issue date:	08/22/2014
From:	Bielby M; NRC/RGN-III/DRS/OLB
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ML13093A443	List: ML15126A524; ML15126A536; ML15126A543; ML15126A554; ML15126A572;
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RO APPLICANT EXAMINATION HANDOUTS

I TITLE: I ALARM RESPONSE PROCEDURE C47047 Rev. 49 Page 1 of 2 ANNUNCIATOR LOCATION. 47047 R-25 Alarm SPENT FUEL POOL AIR High Radiation Level Alarm MONITOR A ESF Equipment Actuation Approximate Setpoints SPENT FUEL POOL AIR Tripped Reset MONITOR A 4X103 CPM Not Specified SER Input Point: (0847)

Address: (24W09)

AUTOMATIC ACTIONS

1. Stops 121 Spent Fuel Pool Normal Supply Fan which upon stopping CLOSES inlet damper CD-34008.

2. Stops 121 Spent Fuel Pool Normal Exhaust Fan which upon stopping CLOSES discharge damper CD-34004.

3. CLOSES Unit 1 Containment In-Service Purge Supply valve CV-31634 and exhaust valve CV-31311.

4. CLOSES Unit 2 Containment In-Service Purge Supply valve CV-31636 and exhaust valve CV-31315.

5. Starts 121 Spent Fuel and In-Service Purge Exhaust Fan which upon starting OPENS exhaust damper MD-32011 and starts filter heater.

6. OPENS 121 Spent Fuel Exhaust damper CD-34010.

INITIAL ACTIONS

1. lE CPM meter deflection is at OR near background level AND there is no ESF Equip Alarm, THEN:

Reset the Hi Radiation Alarm

Inform System Engineer of the spike.

2. lE meter deflection is above OR near CPM setpoint, OR the Hi Rad Level Alarm cannot be reset in Step 1, THEN verify AUTOMATIC ACTIONS have occurred.

3. Check radiation level by observing redundant monitor R-31 on RD panel.

I TITLE:! ALARM RESPONSE PROCEDURE C47047 c Rev. 49 Page 2 of 2 ANNUNCIATOR LOCATION. 47047 R-25 INITIAL ACTIONS (Continued)

4. IF fuel handling is in progress, THEN refer to:

D5.1 AOP1, SFP AREA EVACUATION I NON REFUELING.

OR

D5.2 AOP4, SFP AREA EVACUATION I REFUELING.

5. Notify Radiation Protection Group.

SUBSEQUENT ACTIONS NOTE: The conditions of the plant during this procedure may involve the Emergency Plan. Recommend to the Shift Supervisor to consider classification per F3-2.

1. Monitor 1R-22 and 2R-22 for indication of release activity.

2. Align 1R-11/1R-12 to sample Shield Building Stack per C11, RADIATION MONITORING SYSTEM.

3. !E radiation monitor malfunctioned, THEN refer to C11, RADIATION MONITORING SYSTEM for possible additional required action.

INSTRUMENTS & REFERENCES

1. Actuating device (29020).

2. Flow Diagrams NF-39600, NF-39602-1, NF-39602-2.

3. Logic Diagram NF-40750-2.

4. H4, Offsite Dose Calculations Manual.

I TITLE: I ALARM RESPONSE PROCEDURE C47048

(~ Rev. 45 Page 1 of 2 ANNUNCIATOR LOCATION. 47048 R-31 Alarm SPENT FUEL POOL AIR High Radiation Level MONITOR B Alarm ESF Equipment Actuation Approximate Setpoints SPENT FUEL POOL AIR Tripped Reset MONITOR B 4x103 CPM Not Specified SER Input Point: (0874)

Address: (24W08)

AUTOMATIC ACTIONS

1. Stops 121 Spent Fuel Pool Normal Supply Fan which upon stopping CLOSES inlet damper CD-34008.

2. Stops 121 Spent Fuel Pool Normal Exhaust Fan which upon stopping CLOSES discharge damper CD-34004.

3. CLOSES Unit 1 Containment In-Service Purge Supply valve CV-31633 and Exhaust valve CV-31310.

4. CLOSES Unit 2 Containment In-Service Purge Supply valve CV-31635 and Exhaust valve CV-31314.

5. Starts 122 Spent Fuel and In-Service purge Exhaust Fan which upon starting OPENS exhaust damper MD-32007 and starts filter heater.

6. OPENS 122 Spent Fuel Special Exhaust damper CD-34009.

INITIAL ACTIONS

1. lE CPM meter deflection is at OR near background level AND there is no ESF Equipment Alarm, THEN:

Reset the Hi Radiation Alarm

Inform System Engineer of the spike.

2. IF meter deflection is above OR near CPM Setpoint, OR the Hi Rad Level Alarm cannot be reset in Step 1, THEN verify AUTOMATIC ACTIONS have occurred.

3. Check radiation level by observing redundant monitor R-25 on RD panel.

(

I TITLE: I ALARM RESPONSE PROCEDURE C47048 c Rev. 45 Page 2of2 ANNUNCIATOR LOCATION. 47048 R-31 INITIAL ACTIONS (Continued)

4. lE fuel handling is in progress, THEN refer to:

D5.1 AOP1, SFP AREA EVACUATION I NON REFUELING.

OR

D5.2 AOP4, SFP AREA EVACUATION I REFUELING.

5. CLOSE all pool enclosure doors.

6. Notify Radiation Protection Group.

SUBSEQUENT ACTIONS NO TE: The conditions of the plant during this procedure may involve the Emergency Plan. Recommend to the Shift Supervisor to consider classification per F3-2.

1. Monitor 1R-22 and 2R-22, for indication of release activity.

2. Align 2R-11/2R-12 to sample Shield Building Stack per C11, RADIATION MONITORING SYSTEM.

3. lE radiation monitor malfunctioned, THEN refer to C11, RADIATION MONITORING SYSTEM, for possible additional required action.

INSTRUMENTS & REFERENCES

1. Actuating device (29043).

2. Flow Diagrams NF-39600, NF-39602-1, NF-39602-2.

3. Logic Diagram NF-40750-2.

4. H4, Offsite Dose Calculations Manual.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT OPERATING PROCEDURE

,--*------- --------- I I NUMBER: I I

I c 1 1

11 INSERTION LIMITS WITH 100 STEP OVERLAP UNITS 1 AND 2 I

FIG C1 REV:

s 1

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Page 1of3

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REACTOR POWER(%)

l 0.C. REVIEW DATE: ! OWNER: i EFFECTIVE DATE l ! i i1____________________

6/21/04 Kapitz I iL ________________ -*-----**-*-*-----------*---*---------*------' 6/21/04 ____j

PRAIRIE ISLAND NUCLEAR GENERATING PLANT OPERATING PROCEDURE

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! NUMBER:

c INSERTION LIMITS WITH 100 STEP OVERLAP UNITS 1 AND 2 FIG c1-s REV:

Page 2ofJ 7

1*

1 POWER ! BANK B INSERTION LIMIT BANK C INSERTION LIMIT i BANK D INSERTION LIMIT I i

0 I 203 I 75 2 208 80 i 4 212 I 84 I l

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16 113 18 118 20 123 22 127 0 24 132 4 26 137 9 28 142 14 30 146 18 32 151 23 34 156 28 36 161 33 38 165 37 40 170 42 42 I I

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT OPERATING PROCEDURE 1----c. ------,I INSERTION LIMITS WITH 100 STEP NUMBER' FIG c1-s I L___ _ _ _ _ _ J_______ OVERLAP u_N_1_T_s__1_A_N_o_2_ _ _ _ _ _:---R_E_~a-: :--ii 9_e_3_0 _t POWER BANK B INSERTION LIMIT BANK C INSERTION LIMIT BANK D INSERTION LIMIT I 72 118 74 I I 123 76 I 128 78

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Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits.

LCO 3.1.4 Al I shutdown and control rods shall be OPERABLE.

Individual actual rod positions shall be within 24 steps of their group step counter demand position when the demand position is between 30 and 215 steps, or within 36 steps of their group step counter demand position when the demand position :::; 30 steps, or:=: 215 steps.

NOTE-----------------------------------------

Individua1 RPis may be outside their limits for.::; 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months following substantial rod movement.

APPLICABILTIY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod( s) A.l.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. limits provided in the COLR.

OR A.1.2 Initiate boration to restore l hour SDM to \Vithin limit.

AND A.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Prairie Island Unit 1 **-Amendment No . .f.§.8.. 160 I Units 1 and 2 3.1.4-1 Unit 2 *- Amendment No . .f.49, 151

RO APPLICANT EXAMINATION

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

1. P8184L-004 100/007 EA2.03/4.2/4.4/3E//P8100/B8//2014 ILT NRC R01 Given the following conditions:

- A MANUAL reactor trip has been initiated.

- The following indications are noted on the Control Board:

What is the status of the Reactor Trip Undervoltage and Shunt Trip Coils?

Undervoltage Coils Shunt Trip Coils A. ENERGIZED ENERGIZED B. ENERGIZED DE-ENERGIZED C. DE-ENERGIZED ENERGIZED D. DE-ENERGIZED DE-ENERGIZED 1-F Justifications:

a. Incorrect. Plausible as ST coils are energized and reactor trip breakes are open; however, in this case the UV coils would be de-energized.

b. Incorrect. Plausible if examinee incorrectly reverses ST & UV coil functions and confuses reactor trip breaker indications.

c. Correct.

d. Incorrect. Plausible as UV coils would be de-energized; however, in this case the ST coils would be energized and reactor trip breakers would be open.

Page 1

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

E007 Reactor Trip EA2.03:

Ability to determine or interpret the following as they apply to a reactor trip:

Reactor trip breaker position Technical Reference(s): B8 pg 13 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-004 Obj. 3E Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 2

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

2. P8197L-012 222/008 EPE 2.4.47/4.2/4.2/6//P8100/P8197L-012//2014 ILT NRC R02 Given the following conditions:

- The crew has just completed the immediate actions of 1E-0, Reactor Trip or Safety Injection.

- The ERCS SAS screen is as follows:

What type of accident is occurring?

A. Uncontrolled Depressurization of Both Steam Generators B. Small Break LOCA in the Pressurizer Vapor Space C. Small Break LOCA in the A Loop Cold Leg D. Large Break LOCA in the B Loop Hot Leg Page 3

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-PEO Justifications:

a. Incorrect. Plausible as S/G pressures and levels are reading the same; however, in this case neither S/G is depressurizing in an uncontrolled manner nor completely depressurized.

b. Correct.

c. Incorrect. Plausible as ome indications are similar to a small break LOCA (eg CTMT water level &

pressure, decreased Tavg, yellow path on integrity, and SI filling the PRZR); however, in this case RCS would be more subcooled and PRZR level would not be rising rapidly.

d. Incorrect. Plausible as some indications are similar to a large break LOCA (eg CTMT water level &

pressure, decreased Tavg, and yellow path on integrity); however, in this case the RCS is not completely depressurized and with SI pumps able to fill the PRZR, the RCS would be much more subcooled.

K/A Number:

E008 Pressurizer Vapor Space Accident 2.4.47:

Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Technical Reference(s): P8197L-012 pages 58 - 60.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 6 Question Source: Bank # _______

Modified Bank # _ __

New ____X___

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

10 CFR Part 55 Content:

55.41 __5___

55.43 _____

Comments:

Page 4

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

3. P8197L-012 013/009 EK1.01/4.2/4.7/10//P8100/PI-OPS-GFE-014L//2014 ILT NRC R03 Which of the following correctly describes the reflux boiling flow path during a small break LOCA?

Steam enters the Steam Generator U-tubes via the ____ _ leg where the steam condenses and re-enters the core area via the ____ __ leg.

A. HOT HOT B. HOT COLD C. COLD HOT D. COLD COLD 1-D Justifications:

a. Correct.

b. Incorrect. Plausible as steam enters the SG u-tubes via the hot leg; however, in this case the condensed steam returns to the core via the hot leg.

c. Incorrect. Plausible as the condensed steam returns to the core via the hot leg; however, in this case the steam initially enters the SG u-tubes via the hot leg as well.

d. Incorrect. Plausible if examinee incorrectly believes that the reflux boiling flow path occurs in the cold leg.

Page 5

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

E009 Small Break LOCA EK1.01:

Knowledge of the operational implications of the following concepts as they apply to the small break LOCA:

Natural circulation and cooling, including reflux boiling.

Technical Reference(s): PI-OPS-GFE-014L page 25.

Proposed references to be provided to applicants during examination: None Learning Objective: PI-OPS-GFE-014L Obj. 10 Question Source: Bank # _P8197L-012 013_

Modified Bank # _ __

New _______

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __X__

Comprehension or Analysis ___ _

10 CFR Part 55 Content:

55.41 __14___

55.43 ____ _

Comments:

Page 6

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

4. P8180L-002 034/011 EK2.02/2.6*/2.7*/7B//P8100/NF-39252/B18D/2014 ILT NRC R04 Given the following conditions:

- CA-1-3, 12 CS SUCT FROM CA STANDPIPE CV-31938 INLT ISOL, is CLOSED.

- A Large Break LOCA occurs.

- Containment pressure peaks at 25 psig.

- No operator actions are taken.

- Drawing NF-39252, CS System, is provided.

12 Containment Spray Pump is...

A. NOT running.

B. running and cavitating.

C. running and delivering spray flow with caustic.

D. running and delivering spray flow without caustic.

3-PEO Justifications:

a. Incorrect. Plausible as Containment Pressure has not exceeded the design basis of 46 psig; however, the Containment Spray System auto actuates at 23 psig.

b. Incorrect. Plausible if examinee believes flow from the CS Pumps is only from the Caustic Standpipe; however, flow is also coming from the RWST.

c. Correct.

d. Incorrect. Plausible as most ECCS systems do not have redundant suction valves for each train.

Page 7

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

E011 Large Break LOCA EK2.02:

Knowledge of the interrelations between the and the following Large Break LOCA:

Pumps Technical Reference(s): B18D pages 9 & 13, NF-39252 Proposed references to be provided to applicants during examination: NF-39252 (11 x 17)

Learning Objective: P8180L-002 Obj. 7B Question Source: Bank # P8180L-002 034 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 8

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

5. P8170L-002 064/015/017 AK3.02/3.0/3.1/5B//P8100/C3//2014 ILT NRC R05 Given the following conditions:

- Unit 1 is at 100% power.

- Component Cooling flow to 11 RCP is 0 GPM.

- Seal injection flow to 11 RCP is 8 gpm.

- Reactor Gap/Support Cooling Air flow is normal.

11 RCP will be stopped to prevent...

A. pump radial bearing damage.

B. motor bearing damage.

C. stator winding damage.

D. pump seal damage.

1-P Justifications:

a. Incorrect. Plausible if examinee incorrectly believes the pump radial bearings are cooled by CC; however, in this case the radial bearings are cooled by seal injection which is normal.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly believes the stator windings are cooled by CC; however, in this case they are cooled by Rx Support cooling air flow.

d. Incorrect. Plausible as seal damage would occur if BOTH CC and Seal Injection was lost; however, in this case only CC is lost.

Page 9

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

015/017 Reactor Coolant Pump Malfunctions AK3.02:

Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

CCW lineup and flow paths to RCP oil coolers Technical Reference(s): C3 pages. 4; B3 pages 5, 13, & 14.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-002 Obj. 5B Question Source: Bank # P8170L-002 049 Modified Bank #

New Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

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

55.41 3 55.43 Comments:

Page 10

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

6. P8170L-002 092/022 AA1.09/3.2/3.3/5//P8100/1C12.1 AOP1/B12A/2014 ILT NRC R06 Given the following conditions:

- Unit 1 is at 100% power.

- The crew has entered 1C12.1 AOP1, Loss of RCP Seal Injection, due to loss of all charging pumps.

- 13 Charging pump has been started.

- Normal Letdown has been restored with one 40 gpm orifice.

- 11 RCP Seal Water Injection Flow is at 5 gpm.

- 12 RCP Seal Water Injection Flow is at 5 gpm.

- Charging Pump Header Pressure is at 2325 psig.

- Charging flow to the Regen HX is at 8 gpm.

- The 13 Charging Pump Speed Controller and Charging Line Flow Controller are aligned as follows:

Question continued on next page.

Page 11

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

6. P8170L-002 Question 092/022 AA1.09/3.2/3.3/5//P8100/1C12.1 continued on next page. AOP1/B12A/2014 ILT NRC R06 Question continued from previous page.

How will the following controllers be adjusted to restore seal injection and charging header flow to normal?

13 CHG PMP CHG LINE FLOW SPEED CONT CONT CV-31198 SPEED DIAL SETPOINT DIAL A. CLOCKWISE CLOCKWISE B. CLOCKWISE COUNTER-CLOCKWISE C. COUNTER-CLOCKWISE CLOCKWISE D. COUNTER-CLOCKWISE COUNTER-CLOCKWISE 2-RI Justifications:

a. Correct.

b. Incorrect. Plausible as adjusting the dials in this manner will restore seal injection; however, in this case it will cause charging header pressure to rise above the relief setpoint and regen HX flow will not match letdown flow.

c. Incorrect. Plausible as adjusting CLFC CW will raise seal injection flow; however, in this case adjusting CCP CCW will decrease charging flow.

d. Incorrect. Plausible if examinee incorrectly believes the CCP speed controller is reverse acting and the charging line flow controller is NOT reverse acting and therefore incorrectly believes both controllers need to be turned counter-clockwise."

Page 12

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

022 Loss of Reactor Coolant Makeup AA1.09:

Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Makeup:

RCP seal flows, temperatures, pressures, and vibrations Technical Reference(s): 1C12.1 AOP1 pg 4; B12A pages 23-25; 1C12.1 page 9.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-002 Obj. 5 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 13

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

7. P8197L-012 226/025 AA2.01/2.7/2.9/18//P8100/1ES-1.2/F3-17.2/2014 ILT NRC R07 Given the following conditions:

- A LOCA has occurred on Unit 1.

- Both trains of RHR are in service and are aligned to Sump B.

- Low head recirculation is being monitored per F3-17.2, Long Term Core Cooling.

- The following parameters are noted in the Control Room:

The above information indicates ____________________ blockage.

A. 11 RHR Heat Exchanger B. 12 RHR Heat Exchanger C. Sump B Strainer D. Fuel Assembly 3-PEO Justifications:

a. Incorrect. Plausible as F3-17.2 Table 2 lists RHR HX Blockage as potential flow blockage. Also plausible if examinee incorrectly believes 11 RHR HX is blocked and 12 RHR HX is not blocked because 11 RHR disch pressure is higher than 12 RHR disch pressure. This choice is NOT correct because the RHR discharge pressure would increase instead of decrease for RHR HX blockage.

b. Incorrect. Plausible as F3-17.2 Table 2 lists RHR HX Blockage as potential flow blockage. Also plausible if examinee incorrectly believes 12 RHR HX is blocked and 11 RHR HX is not blocked because 12 RHR flow is lower than 11 RHR flow. This choice is NOT correct because the RHR discharge pressure would increase instead of decrease for RHR HX blockage.

c. Correct. Since RHR pump motor current, RHR Pump Suction pressure, RHR Pump Discharge are all decreasing, this indicates Sump B Strainer Blockage per F3-17.2 Table 2.

d. Incorrect. Plausible as F3-17.2 Table 2 lists Fuel Assembly Blockage as a potential flow blockage.

Also plausible as CETCs are increasing; however, in this case RHR flows and pressures are not STABLE; therefore there is no blockage of the fuel assembly.

Page 14

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Statement:

025 Loss of Residual Heat Removal System AA2.01:

Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System:

Proper amperage of running LPI/decay heat removal/RHR pump(s).

Technical Reference(s): 1ES-1.2 pg 8; F3-17.2 Table 2 pg 12 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 18 Question Source: Bank #:

Modified Bank #:

New: X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 5 55.43 Comments:

Page 15

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

8. P8172L-002 088/026 2.2.38/3.6/4.5/11//P8100/T.S. 3.7.7//2014 ILT NRC R08 Given the following conditions:

- Unit 1 is at 100% power.

- Unit 2 is in Mode 3.

What is the MINIMUM number of Component Cooling trains required to be OPERABLE in order to NOT enter any LCO Action Statements for either unit?

A. 1 B. 2 C. 3 D. 4 1-B Justifications:

a. Incorrect. Plausible if examinee incorrectly believes no CC trains are required for Unit 2 because Unit 2 is in Mode 3 and only one CC train is required for Unit 1.

b. Incorrect. Plausible if examinee incorrectly believes no CC trains are required for Unit 2 because Unit 2 is in Mode 3.

c. Incorrect. Plausible if examinee incorrectly believes only one CC is required for Unit 2 because it is in Mode 3.

d. Correct. 2 pumps per unit in Modes 1-4.

Page 16

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

026 Loss of Component Cooling Water 2.2.38:

Knowledge of conditions and limitations in the facility license.

Technical Reference(s): TS 3.7.7 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-002 Obj. 11 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 4 55.43 Comments:

Page 17

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

9. P8197L-014 183/0029 EK1.03/3.6/3.8/7//P8100/1FR-S.1//2014 ILT NRC R09 Given the following conditions:

- The crew is on step 4 of 1FR-S.1, Response to Nuclear Power Generation/ATWS.

The crew will __________ the RCS from the _________________________ tank(s).

A. DILUTE Reactor Make Up B. DILUTE Condensate Storage C. BORATE Boric Acid Storage D. BORATE Refueling Water Storage 2-RI Justifications:

a. Incorrect. Plausible if examinee incorrectly believes removing boron will add negative reactivity. Also, RMU is the normal source for dilution.

b. Incorrect. Plausible if examinee incorrectly believes removing boron will add negative reactivity. CST plausible as this is a source of unborated water; however, it used for secondary systems.

c. Correct.

d. Incorrect. Plausible as boration is the correct path; however, in this case RWST would not be used unless normal and emergency boration failed. The examinee is not being told that the former has failed.

Page 18

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

029 Anticipated Transient Without Scram (ATWS)

EK 1.03:

Knowledge of the operational implications of the following concepts as they apply to the ATWS:

Effects of boron on reactivity Technical Reference(s): 1FR-S.1 pg. 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 7 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 1 55.43 Comments:

Page 19

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

10. P8197L-013 115/038 EK2.01/2.2*/2.2/8//P8100/E-3//2014 ILT NRC R10 Given the following conditions:

- A tube rupture has occurred in 11 Steam Generator.

- 11 Steam Generator narrow range level is 51% and rising.

- Pressurizer level is 35% and stable.

- Containment pressure is 1 psig.

- The crew is on step 29 of 1E-3, Steam Generator Tube Rupture.

The crew will...

A. turn on pressurizer heaters.

B. depressurize the RCS.

C. lower charging flow.

D. raise charging flow.

Page 20

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-SPR Justification:

a. Incorrect. Plausible if examinee misses that 11 SG level is INCREASING vice DECREASING.

b. Correct. Adverse containment does NOT exist and 11 SG NR level is increasing; therefore, the correct action is to "depressurize the RCS using step 29b".

c. Incorrect. Plausible if examinee incorrectly uses 11 NR SG at level of 51% to determine actions on table in step 29 vice pressurizer level.

d. Incorrect. Plausible for pressurizer level of 35% IF adverse containment existed; however, in this case CTMT pressure is less than 5 psig and therefore NOT adverse.

K/A Statement:

038 Steam Generator Tube Rupture EK2.01:

Knowledge of the interrelations between the and the following a SGTR:

Valves Justification for K/A less than 2.5:

This question requires RO knowledge of when to perform a RCS depressurization using pressurizer spray valves during a SGTR event. Based on past experience at Prairie Island, this knowledge is important to ROs.

Technical Reference(s): 1E-3, Step 29 pg. 19 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-013 Obj. 8 Question Source: Bank #: P8197L-013 110 Modified Bank #:

New:

Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 5 55.43 Comments:

Page 21

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

11. P8180L-007 110/054 AK3.03/3.8/4.1/3//P8100/1E-0/1C28.1, B28B/2014 ILT NRC R11 Given the following conditions:

- Unit 1 is at 55% power.

- 11 Main Feedwater pump is OOS.

- 12 Main Feedwater pump trips on overcurrent.

- AFW flow and pressures are as follows:

In order to maintain AFW pump discharge pressure within limits, the crew will THROTTLE...

A. OPEN MV-32238, 11 TD AFWP to 11 SG.

B. OPEN MV-32381, 12 MD AFWP to 11 SG.

C. CLOSE MV-32239, 11 TD AFWP to 12 SG.

D. CLOSE MV-32382, 12 MD AFWP to 12 SG.

3-SPK Justifications:

a. Incorrect. Plausible if examinee incorrectly believes 11 TD AFWP should be less than 1000 psig.

b. Incorrect. Plausible if examinee incorrectly believes opening 12 MD AFWP MV will raise pressure.

c. Incorrect. Plausible as this will raise 11 AFW Pump discharge pressure; however, 12 AFW Pump discharge pressure is below the 1000 psig low limit and 11 AFWP is not.

d. Correct. AFWP discharge pressures SHALL be maintained greater than 1000 psig.

Page 22

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

054 Loss of Main Feedwater AK3.03:

Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW):

Manual control of AFW flow control valves Technical Reference(s): 1E-0 pg 6; 1C28.1 pg 6, B28B pg 17 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007 Obj. 3 Question Source: Bank # P8180L-007 106 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 4 55.43 Comments:

Page 23

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

12. P8186L-005 036/055 EA1.04/3.5/3.9/7A//P8100/ECA-0.0/B20.8/2014 ILT NRC R12 Given the following conditions:

- The crew is performing 1ECA-0.0, Loss of All Safeguards AC Power.

- Attachment H, DC Bus Load Shed, is complete.

- The picture below shows which bistable lights are LIT and NOT LIT.

Based on the Control Board indications above, which Instrument AC Inverters did the out-plant operators DE-ENERGIZE?

A. 11 and 12 B. 12 and 13 C. 13 and 14 D. 11 and 14 3-SPK Justifications:

a. Incorrect. Plausible as 12 INV is de-energized; also if examinee incorrectly believes 11 INV supplies RED Channel. 11 INV supplies Inst. Bus 111, which is Channel II, WHITE Channel.

b. Correct.

c. Incorrect. Plausible as 13 INV is de-energized; also if examinee incorrectly believes 14 INV supplies BLUE Channel.

d. Incorrect. Plausible if examinee incorrectly believes 11 & 14 INVs supply RED and BLUE Channels.

Page 24

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

056 Loss of Offsite and Onsite Power (Station Blackout)

EA1.04:

Ability to operate and monitor the following as they apply to a Station Blackout:

Reduction of loads on the battery Technical Reference(s): B20.8 pg. 7 & 12; 1ECA-0.0 Att. H pg. 2 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-005 Obj. 7A Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _ ___

Comprehension or Analysis __X __

10 CFR Part 55 Content:

55.41 __7 __

55.43 __ ___

Comments:

Page 25

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

13. P8186L-008 047/056 AA2.54/2.9/3.0/7A//P8100/1C20.5 AOP1/B20.5/2014 ILT NRC R13 Given the following conditions:

Bus 15 is powered from...

A. D1.

B. 1RY.

C. CT-11.

D. Bus 25.

Page 26

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 1-I Justifications:

a. Correct.

b. Incorrect. Plausible as 1RY breaker flag still indicates closed; however, in this case the breaker position light shows open and 1RY is de-energized.

c. Incorrect. Plausible if examinee confuses breaker indications.

d. Incorrect. Plausible if examinee incorrectly believes green light indication means breaker is closed and incorrectly believes BKR 15-7 provides power to a load vice power to Bus 15.

K/A Number:

056 Loss of Offsite Power AA2.54:

Ability to determine and interpret the following as they apply to the Loss of Offsite Power:

Breaker position (remote and local)

Technical Reference(s): B20.5 pgs. 9,10 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-008 Obj. 7A Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ __

10 CFR Part 55 Content:

55.41 __7 __

55.43 __ ___

Comments:

Page 27

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

14. P8186L-015 026/057 2.1.30/4.4/4.0/3//P8100/C20.8AOP1/1C20.8/2014 ILT NRC R14 Given the following conditions:

- The crew is in 1C20.8 AOP1, Abnormal Operation, Instrument AC Inverters.

- 11 Inverter has the following indications:

Question continued on next page.

Page 28

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

14. P8186L-015 026/057 2.1.30/4.4/4.0/3//P8100/C20.8AOP1/1C20.8/2014 ILT NRC R14 Question continued from previous page.

The 11 Instrument Inverter Panel is located in the _______________ Building Battery Room and is receiving power from ________________.

A. Turbine 11 Battery B. Turbine MCC 1AC1 C. Service 11 Battery D. Service MCC 1AC1 3-SPK Justifications:

a. Incorrect. Plausible as 11 inverter is located in TB; however, in this case 11 inverter is receiving power from its alternate source.

b. Correct.

c. Incorrect. Plausible as the SB does have a battery room with inverters; however, they are not the SG instrument inverters referenced in the procedure.

d. Incorrect. Plausible as 11 inverter is receiving power from alternate source MCC 1AC1; however, 11 inverter is located in TB.

Page 29

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

057 Loss of Vital AC Electrical Instrument Bus 2.1.30:

Ability to locate and operate components, including local controls.

Technical Reference(s): 1C20.8 pg. 40; 1C20.8 AOP1 pg. 4, 10; B20.8 pg. 8 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-015 Obj. 3 Question Source: Bank # _ _

Modified Bank # _ __

New _X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X _

10 CFR Part 55 Content:

55.41 __7___

55.43 ____ _

Comments:

Page 30

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

15. P8186L-005 035/058 AK1.01/2.8/3.1*/7A//P8100/1C20.9 AOP1//2014 ILT NRC R15 Given the following conditions:

- Unit 1 is at 100% power.

- 5 minutes later, the crew notes the following ERCS DC1 indications:

- NO operator actions have occurred.

A reactor trip __________ automatically occurred AND Train "A" DC loads are ______________.

A. HAS energized B. HAS de-energized C. HAS NOT energized D. HAS NOT de-energized Page 31

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 2-RI Justifications:

a. Incorrect. Plausible as a reactor trip has occurred and if the examinee incorrectly believes Train A DC loads auto transferred to 12 Battery or is being supplied by 11 Battery; however, the ERCS screen shows Train A DC loads being de-energized.

b. Correct.

c. Incorrect. Plausible if the examinee incorrectly believes that Train A DC loads auto transfered to 12 Battery or is being supplied by 11 Battery and this prevented the reactor UV coils from losing power and causing a reactor trip; however, Train A DC loads are de-energized and will cause a automatic reactor trip.

d. Incorrect. Plausible as Train A DC loads are de-energized and if examinee incorrectly believes that the reactor UV coils require a loss of both DC trains to trip.

K/A Number:

058 Loss of DC Power AK1.01:

Knowledge of the operational implications of the following concepts as they apply to Loss of DC Power:

Battery charger equipment and instrumentation Technical Reference(s): 1C20.9 AOP1 pg. 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-005 Obj. 7A Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X __

10 CFR Part 55 Content:

55.41 __7 __

55.43 __ ___

Comments:

Page 32

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

16. P8178L-005 012/065 AK3.03/2.9/3.4/7D//P8100/C34 AOP1//2014 ILT NRC R16 Given the following conditions:

- Unit 1 is at 100% power.

- CV-31740, Unit 1 Containment Instrument Air Isolation CV, fails CLOSED.

Which of the following is(are) still AVAILABLE?

A. Excess Letdown flowpath from RCS B. Normal Charging flowpath to RCS C. Pressurizer Spray valves D. Pressurizer PORVs 1-F Justifications:

a. Incorrect. Plausible as normal L/D isolates and if examinee incorrectly believes that excess L/D is still available; however, in this case excess L/D will also isolate.

b. Incorrect. Plausible as the seal injection portion is still available; however, in this case normal charging flowpath is not available.

c. Incorrect. Plausible if examinee incorrectly believes the spray valves can be operated from the accumulators.

d. Correct.

Page 33

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

065 Loss of Instrument Air AK3.03:

Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air:

Knowing effects on plant operation of isolating certain equipment from instrument air.

Technical Reference(s): C34 AOP1 pg. 10 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 7D Question Source: Bank # P8178L-005 012 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 4 55.43 Comments:

Page 34

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

17. P8197L-014 190/E05 2.1.20/3.7/4.1/25//P8100/1FR-H.1 BASES//2014 ILT NRC R17 Given the following conditions:

- The crew has entered 1FR-H.1, Response to Loss of Secondary Heat Sink.

- 11 and 12 WR S/G levels are at 8% and slowly lowering.

The Reactor Coolant Pumps will be tripped...

A. to minimize heat addition to the RCS.

B. because forced cooling is no longer required in the RCS.

C. because ECCS injection can adequately remove all decay heat from the core.

D. to prevent RCP seal damage from occurring due to steam formation in the shaft.

1-B Justifications:

a. Correct. 1FR-H.1 step 2&3 basis

b. Incorrect. Plausible as forced flow is desirable for decay heat removal under normal circumstances; however, in this case the benefits of minimizing heat input outweighs the need for forced flow.

c. Incorrect. Plausible as the next step after securing RCPs is to actuate SI; however, that is not the reason for stopping the pumps.

d. Incorrect. Plausible as this is the reason for stopping RCPs if seal cooling is lost; however, in this case it is the loss of secondary heat sink and desire to minimize heat input that drives stopping the pumps.

Page 35

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

E05 Loss of Secondary Heat Sink EK3.2:

Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink):

Normal, abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).

Technical Reference(s): 1FR-H.1 Bases pg. 2 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 25 Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __X___

Comprehension or Analysis ___ _

10 CFR Part 55 Content:

55.41 __14__

55.43 _____

Comments:

Page 36

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

18. P8186L-001 019/077 AA1.01/3.6/3.7/7B//P8100/C22.6 AOP1/C22.6/2014 ILT NRC R18 Given the following conditions:

- Unit 1 is at 100% power.

- An electrical disturbance on the grid has caused the Automatic Voltage Regulator to fail.

- The TSO requests that Unit 1 DELIVER ~50 MVARs to the grid.

- Given the following Control Board indications:

Question continued on next page.

Page 37

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

18. P8186L-001 019/077 AA1.01/3.6/3.7/7B//P8100/C22.6 AOP1/C22.6/2014 ILT NRC R18 Question continued from previous page.

The crew will __________ generator voltage using _________________________.

A. LOWER CS-46366, GEN EXCITER BASE ADJ B. LOWER CS-46377, GEN VOLT REG ADJ C. RAISE CS-46366, GEN EXCITER BASE ADJ D. RAISE CS-46377, GEN VOLT REG ADJ 2-RI Justifications:

a. Incorrect. Plausible as the base adjust will be used; however, in this case voltage must be raised in order to deliver VARs.

b. Incorrect. Plausible if examinee incorrectly believes the GEN VOLT REG ADJ switch is the manual control switch.

c. Correct.

d. Incorrect. Plausible as the voltage must be raised to deliver VARs; however, in this case the base adjuster must be used.

Page 38

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

077 Generator Voltage and Electric Grid Disturbances AA1.01:

Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances:

Grid frequency and voltage Technical Reference(s): C47006-0106 pg 1; C22.6 pgs. 5 & 6; C22.6 AOP1 pg. 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-001 Obj. 7B Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

10 CFR Part 55 Content:

55.41 __7 __

55.43 __ ___

Comments:

Page 39

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

19. P8184L-002 102/032 AK1.01/2.5/3.1/7A//P8100/C1B/1C51/2014 ILT NRC R19 Given the following conditions:

- Unit 1 Reactor startup is in progress.

- Given the following Control Board indications:

The SRNI _______ High Voltage Power Supply has FAILED and further positive reactivity additions are ________________.

A. N31 ALLOWED B. N31 NOT ALLOWED C. N32 ALLOWED D. N32 NOT ALLOWED Page 40

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-PEO Justifications:

a. Incorrect. Plausible as N31 is the only meter NOT reading low in the scale. Also plausible if examinee incorrectly believes that only one SRNI is required for start up; also if examinee incorrectly believes SRNI HV PS should be off based on IRNI level.

b. Incorrect. Plausible as N31 is the only meter NOT reading low in the scale and as (+) reactivity additions are not allowed with only 1 SRNI channel available; however, in this case it is N32 that has failed.

c. Incorrect. Plausible as N32 has failed; however, in this case (+) reactivity additions are not allowed.

d. Correct.

K/A Number:

032 Loss of Source Range Nuclear Instrumentation AK1.01:

Knowledge of the operational implications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:

Effects of voltage changes on performance Technical Reference(s): 1C51.2 SRNI N32 Fails Low pg. 1; B9A pgs. 32-33 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-002 Obj. 7A Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 2 55.43 Comments:

Page 41

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

20. P8178L-001B 008/036 AK2.02/3.4/3.9/5A//P8100/C47047 R-25/C47048 R-31/2014 ILT NRC R20 Given the following conditions:

- A fuel assembly is dropped during fuel handling in the Spent Fuel Pool Area.

- R-25, Spent Fuel Pool Air Monitor A, is reading 6000 cpm.

- R-31, Spent Fuel Pool Air Monitor B, is reading 3900 cpm.

- The Spent Fuel Pool Normal and Special Ventilation Fans are aligned per the picture below:

- C47047 R-25 and C47048 R-31 are provided.

The Control Room Operator will place...

A. CS-46589, 122 SPENT FUEL SPECIAL & 21 IN-SERVICE PURGE EXHST FAN, to STOP.

B. CS-46311, 121 SPENT FUEL SPECIAL & 11 IN-SERVICE PURGE EXHST FAN, to STOP.

C. CS-46071, 121 SPENT FUEL POOL MAKE-UP AIR FAN, to STOP AND CS-46079, 121 SPENT FUEL POOL NORMAL EXHST FAN, to STOP.

D. CS-46071, 121 SPENT FUEL POOL MAKE-UP AIR FAN, to START AND CS-46079, 121 SPENT FUEL POOL NORMAL EXHST FAN, to START.

Page 42

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-SPR Justifications:

a. Incorrect. Plausible as the R-31 is below setpoint for auto starting 122 SFP Special Fan and examinee may incorrectly believe the fan needs to be stopped.

b. Incorrect. Plausible as 121 SFPS fan started prior to R-31 reaching setpoint; however, in this case the ARP specifies that if R-31 is near setpoint then verify auto actions occurred.

c. Correct. Since R-25 is in high alarm. 121 SFP Special Fan will start. 121 SFP Normal Fans should have automatically shut off. Since they did not, they need to be secured by the operator. 122 SFP Special Fan started early, but there is no need to secure since it is near its setpoint.

d. Incorrect. Plausible if examinee believes radiation levels for R-25 and R-31 are below the setpoint and confuse indicating lights with green being running and red being not running.

K/A Number:

036 Fuel Handling Incidents AK2.02:

Knowledge of the interrelations between the Fuel Handling Incidents and the following:

Radiation monitoring equipment (portable and installed)

Technical Reference(s): C47047 R-25 & C47048 R-31; B11 pg. 13 Proposed references to be provided to applicants during examination: C47047 R-25 &

C47048 R-31 Learning Objective: P8178L-001B Obj. 5A Question Source: Bank # P8178L-001B 008 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 11 55.43 Comments:

Page 43

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

21. P8182L-001C 030/060 2.1.32/3.8/4.0/3F//P8100/C21.3.1/C21.3.2/2014 ILT NRC R21 The concentration of OXYGEN at the outlet of the 121 Catalytic Hydrogen Recombiner SHALL be maintained less than or equal to________ by volume to prevent an accidental gaseous radwaste release due to explosion.

A. 2%

B. 10%

C. 12%

D. 21%

1-P Justifications:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes 10% is the [O2] limit; however, in this case 10% is the high hydrogen condition for the WG system.

c. Incorrect. Plausible if examinee incorrectly believes the oxygen limit is 2% above the Hydrogen limit of 10%.

d. Incorrect. Plausible if examinee incorrectly believes that atmospheric [O2] is the limit for the WG system.

Page 44

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Accidental Gaseous Radwaste Release 2.1.32:

Ability to explain and apply system limits and precautions.

Technical Reference(s): C21.3.2 pg. 5, 9; C21.3.1 pg. 13 Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-001C Obj. 3F Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

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

55.41 13 55.43 Comments:

Page 45

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

22. P8178L-002 048/067 AK1.02/3.1/3.9/4//P8100/C31/B31A/2014 ILT NRC R22 Given the following conditions:

- A fire occurred in the Turbine Building.

- 121 Motor Driven Fire pump started AUTOMATICALLY.

- 122 Diesel Driven Fire pump started AUTOMATICALLY.

- The Fire Brigade extinguished the fire with fire hoses.

- The affected portions of the Fire Protection System have been isolated.

121 Motor Driven Fire pump will be shutdown _____________________________ and 122 Diesel Driven Fire pump will be shutdown _____________________________.

A. LOCALLY at the pump LOCALLY at the pump B. LOCALLY at the pump REMOTELY from the Control Room C. REMOTELY from the Control Room LOCALLY at the pump D. REMOTELY from the Control Room REMOTELY from the Control Room 1-T Justifications:

a. Correct.

b. Incorrect. Plausible as 121 MDFP will be shutdown locally; however, in this case 122 DDFP can only be shutdown locally.

c. Incorrect. Plausible as 122 DDFP will be shutdown locally and 121 can be shutdown remotely; however, in this case since 121 auto started it must be shutdown locally.

d. Incorrect. Plausible as 121 can be shutdown remotely; however, in this case since 121 auto started it must be shutdown locally. Also, if examinee incorrectly believes 122 DDFP has a remote CR shutdown feature.

Page 46

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

067 Plant Fire on site AK1.02:

Knowledge of the operational implications of the following concepts as they apply to Plant Fire on Site:

Fire fighting Technical Reference(s): C31 pgs. 8-19; B31A pgs 8-12.

Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-002 Obj. 4 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 8 55.43 Comments:

Page 47

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

23. P8172L-001A 134/076 AK2.01/2.6/3.0/5//P8100/B11//2014 ILT NRC R23 Given the following conditions:

Question continued on next page.

Page 48

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

23. P8172L-001A 134/076 AK2.01/2.6/3.0/5//P8100/B11//2014 ILT NRC R23 Question continued from previous page.

There is high activity in the ____________ Coolant System due to a ___________________________.

A. Primary Steam Generator Tube Rupture B. Primary Fuel Element Failure C. Secondary Steam Generator Tube Rupture D. Secondary Fuel Element Failure 2-DR Justifications:

a. Incorrect. Plausible as there is high activity in the primary; however, it is not due to a SGTR.

b. Correct.

c. Incorrect. Plausible as secondary coolant would be high for a SGTR; however, in this case the ERCS indications given show high primary activity. Some ERCS Rad level alarm setpoints vary with the actual rad monitor itself; therefore it is plausible that a radiation level for a ERCS point is high but still green in color. Therefore, the examinee still needs to be familiar with approximately what level is high or normal for any rad monitor.

d. Incorrect. Plausible as a fuel element failure has occurred; however, in this case it would not cause high secondary activity.

Page 49

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

076 High Reactor Coolant Activity AK2.01:

Knowledge of the interrelations between the High Reactor Coolant Activity and the following:

Process radiation monitors Technical Reference(s): B11 pages 23 - 24 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-001A Obj. 5 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 11 55.43 Comments:

Page 50

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

24. P8178L-002 027/E15 EK3.3/2.9/2.9/6A//P8100/FR-Z.2/B31A/2014 ILT NRC R24 Which of the following systems is NOT a source of flooding in Containment in Mode 1?

A. Component Cooling Water B. CFCU Cooling Water C. Reactor Make Up D. Fire Protection 1-S Justifications:

a. Incorrect. Plausible if examinee incorrectly believes the Fire Protection System is aligned to containment during mode 1 and the Component Cooling Water System does not provide cooling to components in Containment.

b. Incorrect. Plausible if examinee incorrectly believes the Fire Protection System is aligned to containment during mode 1 and the CFCU Cooling Water is NOT aligned to containment during mode 1 (i.e. CFCUs are on Chilled Water only during mode 1).

c. Incorrect. Plausible if examinee incorrectly believes the Fire Protection System is aligned to containment during mode 1 and the Reactor Make Up System is NOT a source of flooding in Containment.

d. Correct.

Page 51

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

W/E15 Containment Flooding EK3.3:

Knowledge of the reasons for the following responses as they apply to the (Containment Flooding):

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

Technical Reference(s): B31A pg. 7; FR-Z.2 pg. 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-002 Obj. 6A Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 8 55.43 Comments:

Page 52

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

25. P8180L-009 020/E16 EA1.2/2.9/3.0/4B//P8100/B19//2014 ILT NRC R25 Given the following conditions:

- Unit 1 is in Mode 6.

- 1R-11, Unit 1 Containment Particulate Monitor, is in alarm.

An automatic _____________ of the ________________ system will occur.

A. ACTUATION Containment Purge B. ACTUATION Shield Building Ventilation C. ISOLATION Containment Purge D. ISOLATION Shield Building Ventilation 3-PEO Justifications:

a. Incorrect. Plausible if examinee incorrectly believes CTMT Purge has an auto actuation feature to clean up CTMT air on Hi Rad.

b. Incorrect. Plausible as SBV has an auto actuation feature; however, it is only from an SI signal.

c. Correct.

d. Incorrect. Plausible as an isolation will occur; however, it is for CTMT Purge.

Page 53

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

E16 High Containment Radiation EA1.2:

Ability to operate and / or monitor the following as they apply to the (High Containment Radiation):

Operating behavior characteristics of the facility.

Technical Reference(s): B19 pgs. 16-27 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009E Obj. 4B Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 11 55.43 Comments:

Page 54

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

26. P8197L-012 135/E03 EA2.2/3.5/4.1/12//P8100/ES-1.1//2014 ILT NRC R26 Given the following conditions:

- A small break LOCA has occurred on Unit 1.

- The crew is performing 1ES-1.1, Post LOCA Cooldown and Depressurization.

1ES-1.1 requires the RCS COLD LEG cooldown rate to be maintained less than _____________ in order to ____________________________.

A. 100 °F / hour preclude violating thermal shock limits B. 100 °F / hour minimize outsurge from the pressurizer C. 200 °F / hour preclude violating thermal shock limits D. 200 °F / hour minimize outsurge from the pressurizer 1-B Justifications:

a. Correct.

b. Incorrect. Plausible as 100 is the correct CDR; however, the limit is to preclude thermal shock.

c. Incorrect. Plausible as 200 is a CDR limit for the pressurizer in the PTLR and the reason is for thermal shock; however, in this case the question is for the RCS Cold Leg limit.

d. Incorrect. Plausible as 200 is a CDR limit for the pressurizer in the PTLR.

Page 55

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

E03 LOCA Cooldown and Depressurization EA2.2:

Ability to determine and interpret the following as they apply to the (LOCA Cooldown and Depressurization):

Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

Technical Reference(s): 1ES-1.1 step 6 bases pg 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 12 Question Source: Bank # _P8197L-012 135__

Modified Bank # _ __

New _______

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ __

10 CFR Part 55 Content:

55.41 __5___

55.43 _____

Comments:

Page 56

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

27. P8197L-014 184/E08 2.4.9/3.7/3.8/31//P8100/FR-P.1/F-0/2014 ILT NRC R27 Given the following conditions:

- A Tube Rupture occurs on 11 Steam Generator.

- Subsequently, a RED path on INTEGRITY occurs.

The crew will __________ the RCS cooldown rate and __________ RCS pressure.

A. RAISE RAISE B. RAISE LOWER C. LOWER RAISE D. LOWER LOWER 3-SPK Justifications:

a. Incorrect. Plausible as the RCS must be cooled down for a SGTR; however, in this case a RED path on integrity requires the CDR to be lowered to prevent PST.

b. Plausible as this is the correct response for a SGTR; however, the RED path on integrity trumps the strategy of E-3.

c. Incorrect. Plausible as the CDR must be lowered; however, in this case the pressure must also be lowered.

d. Correct.

Page 57

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

E08 Pressurized Thermal Shock 2.4.9:

Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

Technical Reference(s): 1FR-P.1 pg. 3, 10, F-0 pg. 2.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 31 Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge ______

Comprehension or Analysis __X _

10 CFR Part 55 Content:

55.41 __10__

55.43 _____

Comments:

Page 58

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

28. P8170L-002 091/003 A4.02/2.9/2.9/3F//P8100/47012-0203//2014 ILT NRC R28 Given the following conditions:

- C47012-0203, 11 or 12 RCP Hi Vibration, is in alarm.

What is the FIRST action the crew will perform?

A. Initiate logging of RCP vibrations every 20 minutes.

B. Commence a controlled shutdown.

C. Commence a rapid downpower.

D. Immediately trip the reactor.

1-I Justifications:

a. Incorrect. Plausible as this is the correct action for shaft vibrations >8 mils but <10 mils; however, in this case 11 RCP vibrations are >14 mils.

b. Incorrect. Plausible as this is the correct action for shaft vibrations >10 mils.

c. Incorrect. Plausible as rapid downpower is performed for deteriorating plant conditions; however, not for hi RCP vibrations.

d. Correct.

Page 59

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

003 Reactor Coolant Pump System (RCPS)

A4.02:

Ability to manually operate and/or monitor in the control room:

RCP motor parameters Technical Reference(s): C47012-0203 pg. 1 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-002 Obj. 3F Question Source: Bank # P8170L-002 078 Modified Bank #

New Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

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

55.41 3 55.43 Comments:

Page 60

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

29. P8172L-001A 045/004 K6.20/2.5/3.1/7A//P8100/B12A/1C12.1/2014 ILT NRC R29 Given the following conditions:

- Unit 1 is at 100% power.

- 1HC-130, 11 LTDN CC OUTL CV-31202 TEMP CONT STA, output fails to 100%.

- NO operator actions have occurred.

LETDOWN temperature to the Mixed Bed Demineralizer will ___________ and RCS boron concentration will ____________.

A. RISE LOWER B. RISE RISE C. LOWER LOWER D. LOWER RISE Page 61

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-PEO Justification:

a. Incorrect. Plausible LD temp will rise; however, in this case the IX will release boron to the RCS.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly believes that CV-31202 has failed OPEN.

d. Incorrect. Plausible as RCS [B] will rise; however, in this case LD temp will rise.

K/A Number:

004 Chemical and Volume Control System K6.20:

Knowledge of the effect of a loss or malfunction on the following CVCS components:

Function of demineralizer, including boron loading and temperature limits Technical Reference(s): 1C12.1 pg. 66; B12A pgs. 8-10; C47015-0408 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-001A Obj. 7A Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 5 55.43 Comments:

Page 62

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

30. P8197L-010 052/004 2.4.6/3.7/4.7/21//P8100/ECA-0.0 BASES//2014 ILT NRC R30 Given the following conditions:

- The crew is isolating RCP seals per 1ECA-0.0, Loss of All Safeguards AC Power.

VC-14-1 and VC-14-2, RCP Seal Injection valves, are closed to prevent...

A. thermal shock to RCP seals and shaft when a charging pump is started.

B. steam introduction to CC system from RCP thermal barrier heating.

C. seal leakoff line pressure from rising to the relief valve setpoint.

D. seal leakage from overfilling the VCT.

1-B Justifications:

a. Correct.

b. Incorrect. Plausible as this is the correct purpose for closing CC return valves.

c. Incorrect. Plausible as this purpose is stated in step 8 bases; however, it is for RCP seal return valves and it is a desireable result vice trying to prevent it.

d. Incorrect. Plausible as this is a correct purpose for closing RCP seal return valves.

Page 63

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

004 Chemical and Volume Control System 2.4.6:

Knowledge of EOP mitigation strategies.

Technical Reference(s): 1ECA-0.0 Bases pg. 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-010 Obj. 21 Question Source: Bank # _P8197L-011 059_

Modified Bank # _ __

New _______

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __X__

Comprehension or Analysis ___ _

10 CFR Part 55 Content:

55.41 __10___

55.43 ____ _

Comments:

Page 64

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

31. P8180L-003 059/005 K1.08/2.7/2.8/5D//P8100/B14/15/B35/2014 ILT NRC R31 Given the following conditions:

- Unit 1 is in Mode 4.

- Train ' B'RHR is aligned for shutdown cooling.

- CV-31411, 12 CC HX TCV, fails OPEN.

RHR temperature will __________ and the crew will throttle __________ 12 RHR HX OUTLET FLOW CV.

A. RISE OPEN B. RISE CLOSE C. LOWER OPEN D. LOWER CLOSE 3-PEO Justifications:

a. Incorrect. Plausible if examinee incorrectly believes that CL flow will decrease and cause an increase in RHR temperature.

b. Incorrect. Plausible as RHR outlet flow CV will need to be closed; however, it will be as a result of RHR temperature decreasing.

c. Incorrect. Plausible as RHR temperatures will lower; however, RHR outlet flow CV will need to be closed to reduce flow and increase temperature.

d. Correct.

Page 65

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

005 Residual Heat Removal K1.08:

Knowledge of the physical connections and/or cause effect relationships between the RHRS and the following systems:

SWS Technical

References:

B14 pages 7, 8, 22, 23; B15 pages 10 - 11, 17, 26; B35 pages 19 & 26 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-003 Obj. 5D Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 5 55.43 Comments:

Page 66

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

32. P8197L-006 014/005 K5.05/2.7*/3.1*/3//P8100/DOE FUND HB V 1//2014 ILT NRC R32 Given the following conditions:

- Unit 1 is in Mode 5.

- Pressurizer is filled SOLID.

- 1HC-135, Letdown Line Pressure Control, is in AUTO.

- The Reactor Operator LOWERS RCS temperature by 1°F.

- NO additional operator actions are taken.

RCS pressure will initially ________ and then ________________________ pressure.

A. RISE stabilize at a new HIGHER B. RISE LOWER to near its original C. LOWER stabilize at a new LOWER D. LOWER RISE to near its original 3-PEO Justifications:

a. Incorrect. Plausible if examinee does not understand temperature/pressure relationship for water when plant is water solid.

b. Incorrect. Plausible if examinee does not understand temperature/pressure relationship for water when plant is water solid.

c. Incorrect. Plausible as RCS temperature will lower; however, in this case pressure will raise to nears its original value.

d. Correct.

Page 67

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

005 Residual Heat Removal K5.05:

Knowledge of the operational implications of the following concepts as they apply the RHRS:

Plant response during "solid plant" pressure change due to the relative incompressibility of water Technical Reference(s): DOE Fundamentals Handbook, Thermodynamics, Heat Transfer, and Fluid Flow - Volume 1 page 127.

Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-006 Obj. 3 Question Source: Bank # _____________

Modified Bank # _ P8197L-006 014 __

New _______

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X _

10 CFR Part 55 Content:

55.41 __5___

55.43 ____ _

Comments:

Page 68

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

33. P8180L-004 049/006 K2.01/3.6/3.9/3E//P8100/B18A/B20.5/B28A/2014 ILT NRC R33 Given the following conditions:

- A Large Break LOCA occurs on Unit 1.

- A lockout occurs on Bus 16.

- NO operator actions have occurred.

Which of the following components is RUNNING?

A. 11 SI pump B. 12 RHR pump C. 13 Condensate pump D. 14 Containment Fan Coil Unit 1-I Justifications:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes 12 RHR to be a train A component.

c. Incorrect. Plausible as 13 Cond. pump is not powered from Bus 16; however, it will auto stop due to SI.

d. Incorrect. Plausible as CFCUs will restart after an SI; however, in this case train B components will not re-energize.

Page 69

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

006 Emergency Core Cooling System K2.01:

Knowledge of bus power supplies to the following:

ECCS pumps Technical Reference(s): B18A pg. 5, B20.5 pg. 18, B28A page 7.

Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-004 Obj. 3E Question Source: Bank #

Modified Bank # P8180L-004 019 New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 8 55.43 Comments:

Page 70

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

34. P8170L-003 100/007 K3.01/3.3/3.6/3D//P8100/B4A//2014 ILT NRC R34 Given the following conditions:

- Unit 1 is at 100% power.

- 47012-0406, PRZR RELIEF TANK HI TEMP/LVL/PRESS OR LO LVL, alarms.

- A reactor trip AND Safety Injection occurs.

- After the Safety Injection, the following are noted:

- Containment Radiation Monitor levels are rising.

- Containment humidity is rising.

- Containment pressure is rising.

- 47016-0304, CONTAINMENT SUMP A LEVEL HIGH, is in alarm.

What has caused the above indications?

A. A RCP #1 seal has failed.

B. A Pressurizer PORV is stuck open.

C. A Steam Generator Blowdown piping connection has severed.

D. An Incore Thimble Tube has ruptured at the bottom of the reactor vessel.

3-PEO

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

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

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

d. Incorrect. Plausible as this failure will fill up the thimble tube and leak to the seal table. This will increase radiation levels, humidity, and pressure in containment but will not fill up Sump A.

Page 71

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

007 Pressurizer Relief Tank System K3.01:

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

Containment Technical Reference(s): B4A pg. 23 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj. 3D Question Source: Bank # P8170L-003 100 Modified Bank #

New Question History: Last NRC Exam 2010 NRC ILT EXAM Question Cognitive Level:

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

55.41 3 55.43 Comments:

Page 72

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

35. P8170L-003 115/007 A2.03/2.6/3.2/4A//P8100/47012-0406/1C4/2014 ILT NRC R35 Given the following conditions:

The crew is required to ____________________ in the Pressurizer Relief Tank per A. RAISE level 1C4, Reactor Coolant System B. RAISE pressure C47012-0406, PRZR RELIEF TANK HI TEMP/LVL/PRESS or LO LVL C. LOWER pressure 1C4, Reactor Coolant System D. LOWER temperature C47012-0406, PRZR RELIEF TANK HI TEMP/LVL/PRESS or LO LVL Page 73

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-PEO Justifications:

a. Incorrect. Plausible if examinee incorrectly believes PRT level is low and should be raised for quench volume; however, in this case level is at the high end of the band (71.5% -76%)

b. Incorrect. Plausible if examinee incorrectly believes PRT pressure is below the normal operating pressure (6 psig).

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes PRT temperature is high above alarm setpoint due to Rx Flange Leakoff Temperature; however, in this case PRT temperature is normal.

K/A Number:

007 Pressurizer Relief Tank System A2.02:

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

Abnormal pressure in the PRT Technical Reference(s): 1C4 pg. 7; C47012-0406 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj. 4A Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 3 55.43 Comments:

Page 74

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

36. P8172L-002 090/008 K4.01/3.1/3.3/4E//P8100/B14/47020-0402/2014 ILT NRC R36 Given the following conditions:

- Unit 1 is at 100% power.

- 11 CC pump is RUNNING.

- Bus 15 locks out.

- NO operator actions are taken.

The 11 CC pump is _______________ and the 12 CC pump is _______________.

A. running running B. running NOT running C. NOT running running D. NOT running NOT running 1-I Justifications:

a. Incorrect. Plausible if examinee incorrectly believes 11 CC pump is not powered from Bus 15; also 12 CC pump will be running due to initial low header discharge pressure auto start.

b. Incorrect. Plausible if examinee incorrectly believes 11 CC pump is powered from Bus 16 and 12 CC pump is powered from Bus 15.

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes that the CC pumps do not have a auto start standby feature.

Page 75

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

008 Component Cooling Water K4.01:

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

Automatic start of standby pump Technical Reference(s): B14 pg. 6; C47020-0402 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-002 Obj. 4E Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 76

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

37. P8170L-005 063/010 K3.03/4.0/4.2/3D//P8100/B7/C51.3/2014 ILT NRC R37 Given the following conditions:

- Unit 1 is at 50% power.

- CS-46289, PRZR PRESSURE CONTROL CHANNEL SEL, is in the 2-3 (WHITE-BLUE) position.

- PT-431, Blue Channel Pressurizer Pressure, fails HIGH.

- NO operator actions are taken.

The reactor will trip on ________ pressurizer pressure and Safety Injection will ______________.

A. LOW actuate B. LOW NOT actuate C. HIGH actuate D. HIGH NOT actuate 3-PEO Justifications:

a. Correct. With no operator action, the spray valves will open and lower RCS pressure until reactor trips on low przr pressure and SI. If plant is at 100% power, the reactor will trip on OTdT.

b. Incorrect. Plausible as the reactor will trip on low przr pressure; however, in this case SI will actuate due to open spray valves lowering pressure below 1830 psig.

c. Incorrect. Plausible as SI will actuate and if examinee incorrectly believes that logic is met for hi pressure trip; however, in this case (2 of 3) is required to trip on high pressure.

d. Incorrect. Plausible if examinee incorrectly believes that logic is met for hi pressure trip; however, in this case (2 of 3) is required to trip on high pressure. Also, if examinee incorrectly believes that spray valves will not lower pressure below SI actuation setpoint of 1830 psig.

Page 77

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

010 Pressurizer Pressure Control System K3.03:

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

ESFAS Technical Reference(s): B7 pg. 15-17; 1C51.3 1P-431-High Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-005 Obj. 3D Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 78

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

38. P8197L-012 073/010 K5.02/2.6/3.0*/GFE-003L OBJ 3//P8100/MOLLIER DIAGRAM/STEAM TABLES/2014 ILT NRC R38 Given the following conditions:

- Unit 1 is at 100% power.

- 47012-0109, PRZR SAFETY/RELIEF VALVE FLOW, is in alarm.

- PRT pressure is 20 psig.

What is the approximate expected tail pipe temperature?

A. 165°F B. 260°F C. 305°F D. 652°F 3-SPR Justifications:

a. Incorrect. Plausible if examinee incorrectly subtracts 15# from PRT pressure (20-15=5) to determine tailpiece temperature.

b. Correct. 2235 psig and 650ºF in PRZR; tailpiece downstream to PRT at 20 psig; isenthalpic expansion along the saturation line for 35 psia on Mollier Diagram = 260ºF.

c. Incorrect. Plausible if examinee incorrectly follows entropy line straight up to saturation line vice along the psia line on Mollier Diagram.

d. Incorrect. Plausible if examinee incorrectly believes that no entropy is gained and vapor temperature in PRZR will remain constant down tailpiece to PRT.

Page 79

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

010 Pressurizer Pressure Control System K5.02 Knowledge of the operational implications of the following concepts as the apply to the PZR PCS:

Constant enthalpy expansion through a valve Technical Reference(s): Steam Tables / Mollier Diagram Proposed references to be provided to applicants during examination: Steam Table and Mollier Diagram Learning Objective: PI-OPS-GFE-003L Obj. 3 Question Source: Bank # _P8197L-012 073__

Modified Bank # _ __

New _______

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _ _

Comprehension or Analysis __X __

10 CFR Part 55 Content:

55.41 __14 _

55.43 ____ _

Comments:

Page 80

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

39. P8184L-004 002/012 K6.02/2.9/3.1/3E//P8100/B8//2014 ILT NRC R39 Given the following conditions:

- Unit 1 is at 100% power.

- Pressurizer pressure lowers to 1880 psig.

- The Train ' A'Low Pressurizer Pressure bistable relays FAILED to trip.

The reactor will _________ because Reactor Protection Train ___________________.

A. trip

'A'logic relay actuates B. trip

'B'logic relay actuates C. NOT trip

'A'logic relay does NOT actuate D. NOT trip

'B'logic relay does NOT actuate 2-RI Justifications:

a. Incorrect. Plausible as a reactor trip will occur; however, in this case Train A has failed and will not actuate to de-energize the RTA UV coil.

b. Correct. Only one RP train logic relay is needed to de-energize a reactor trip UV coil to trip the reactor.

c. Incorrect. Plausible as the Train A relay logic will not remove power from the A UV coil; however, in this case a trip will occur because Train B will actuate.

d. Incorrect. Plausible if examinee incorrectly believes that BOTH trains of relay logic are required to actuate to trip the reactor.

Page 81

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

012 Reactor Protection System K6.02:

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

Redundant channels Technical Reference(s): B8 pgs. 9, 10, 13 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-004 Obj. 3E Question Source: Bank # P8184L-004 002 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 82

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

40. P8180L-006 079/013 A1.07/3.6/3.9/3E//P8100/B11/B18C/2014 ILT NRC R40 Given the following conditions:

- Unit 1 is in Mode 5.

- Unit 1 Containment In-Service Purge is in service.

- 1R-12, Unit 1 Containment Gas Monitor, is in alarm.

- 1R-12 is reading 2000 CPM.

A _____________________________ signal will be actuated on Unit 1 and the __________ Containment In-Service Purge valves on both units will be isolated.

A. Containment Isolation Train A B. Containment Isolation Train B C. Containment Ventilation Isolation Train A D. Containment Ventilation Isolation Train B 3-PEO Justifications:

a. Incorrect. Plausible if examinee incorrectly believes 1R-12 generates a CI signal and that Train A will be isolated; however, in this case only CVI signal is generated and Train B valves are isolated.

b. Incorrect. Plausible as Train B valves will be isolated; however, in this case a CI signal is not generated.

c. Incorrect. Plausible as CVI signal is generated; however, in this case Train B valves are isolated.

d. Correct.

Page 83

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

013 Engineered Safety Features Actuation System A1.07:

Ability to predict and/or monitor changes in parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: Containment radiation Technical Reference(s): B11 pg. 13; B18C pg. 14-15; P8182L-002 pg. 26; NF-40762-1 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-006 Obj. 3E Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 11 55.43 Comments:

Page 84

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

41. P8180L-009H 052/022 A2.05/3.1/3.5/4B//P8100/C19.3//2014 ILT NRC R41 Given the following conditions:

- 47019-0607, Containment Condensate Hi Leak Rate, is in alarm.

- 11 Fan Coil Unit Weir Tank level is 11 inches.

- 11 Fan Coil Unit Weir Tank is drained to 0 inches.

- 5 minutes later, 11 Fan Coil Unit Weir Tank level is 11 inches and stable.

- Figure 1 from C19.3, Leakage Within Containment, is provided below.

There is a ___ gpm leak on the 11 Fan Coil Unit.

A. < 1 B. 5 C. 7 D. > 10 Page 85

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-SPR Justifications:

a. Incorrect. Plausible if examinee incorrectly believes weir gate drawing indicates 6 inches must be removed from the height reading due to location of the V-notch.

b. Incorrect. Plausible if examinee incorrectly believes the level reading must be adjusted down by 2 inches since the bottom of the weir tank is at the 2 inch mark.

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes weir gate drawing indicates 6 inches must be added to the height reading due to location of the V-notch.

K/A Number:

022 Containment Cooling System A2.05:

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

Major leak in CCS Technical Reference(s): C19.3 pg. 6 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009H Obj. 4B Question Source: Bank #

Modified Bank # P8180L-009H 050 New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 10 55.43 Comments:

Page 86

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

42. P8172L-002 040/026 K1.02/4.1/4.1/6C//P8100/C14 AOP1//2014 ILT NRC R42 The _________________________ can be operated indefinitely WITHOUT Component Cooling flow and NOT exceed an operating limit.

A. Safety Injection Pump B. Letdown Heat Exchanger C. Containment Spray Pump D. Seal Water Heat Exchanger 1-B Justifications:

a. Incorrect. Plausible if examinee incorrectly believes RWST flow through the SI pump will be enough to prevent the pump from overheating.

b. Incorrect. Plausible if examinee incorrectly believes CC flow is not required for LDHX below Mode 2; however, in this case while the duty of LDHX is Mode 1 & 2, the HX cannot be operated without CC.

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes charging flow to RCP seals will also cool the SWHX; however, in this case CC is required for HX to maintain VCT temperature below 130 degrees.

Page 87

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

026 Containment Spray System K1.02:

Knowledge of the physical connections and/or cause effect relationships between the CSS and the following systems:

Cooling water Technical Reference(s): 1C14 AOP1 pg 11,13 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-002 Obj. 6C Question Source: Bank #

Modified Bank # P8172L-002 040 New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 8 55.43 Comments:

Page 88

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

43. P8180L-002 006/026 A3.01/4.3/4.5/3E//P8100/NF 40320-1/B18D/2014 ILT NRC R43 Given the following conditions:

- Unit 1 is at 100% power.

- 11 Containment Spray pump Local/Remote switch is in LOCAL.

- 11 Containment Spray pump is NOT running.

- A Large Break LOCA occurs on Unit 1.

- Containment pressure reaches 27 psig.

- NO operator actions are taken.

The 11 Containment Spray pump is _________ and MV-32103, 11 Containment Spray pump Discharge Valve, is ___________________.

A. running OPEN B. running cycling OPEN and CLOSED C. NOT running OPEN D. NOT running cycling OPEN and CLOSED 3-PEO Justifications:

a. Incorrect. Plausible as this would be the normal configuration following a P signal; however, in this case the pump is in local/manual and would not auto start and the valve would not remain open.

b. Incorrect. Plausible as the MV will be cycling; however, in this case the breaker would be open due to being in manual and unable to auto close on P signal.

c. Incorrect. Plausible as the pump will not auto start; however, in this case the MV would be cycling due to P signal to open but no breaker closed seal in to maintain MV open.

d. Correct.

Page 89

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

026 Containment Spray System A3.01:

Ability to monitor automatic operation of the CSS, including:

Pump starts and correct MOV positioning Technical Reference(s): B18D pg. 6-8 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-002 Obj. 3 Question Source: Bank # P8180L-002 006 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 90

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

44. P8174L-001 032/039 A4.01/2.9*/2.8*/6A//P8100/B27//2014 ILT NRC R44 Given the following conditions:

- Unit 1 has a loss of Train A DC power.

- The turbine failed to trip automatically or manually.

- CS-46158, A Main Stm Line Isol CV-31098, is placed in CLOSE.

- CS-46159, B Main Stm Line Isol CV-31099, is placed in CLOSE.

What is the status of the 11 and 12 MSIVs?

11 MSIV 12 MSIV A. OPEN OPEN B. OPEN CLOSED C. CLOSED OPEN D. CLOSED CLOSED 3-PEO Justifications:

a. Incorrect. Plausible if examinee incorrectly believes a loss of Train A DC power will prevent the air vent solenoid from energizing and therefore bleeding off the air to close the MSIV.

b. Incorrect. Plausible as 12 MSIV would be closed; however, in this case the 11 MSIV would also close.

c. Incorrect. Plausible as 11 MSIV would be closed; however, in this case the 12 MSIV would also close.

d. Correct. The MSIVs have 2 redundant vent solenoid valves, each powered by Train A and Train B DC respectively, which are located downstream of a common vent header from the MSIVs. A loss of either train DC will remove light indication at the CB for the respective MSIV but will not affect the operator's ability to close the valves. A loss of BOTH trains will prevent the MSIVs from closing.

Page 91

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

039 Main and Reheat Steam System A4.01:

Ability to manually operate and/or monitor in the control room:

Main steam supply valves Technical Reference(s): B27 pgs. 6-8, 21 Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-001 Obj. 6A Question Source: Bank # P8174L-001 032 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 92

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

45. P8174L-006 035/059 2.4.35/3.8/4.0/7A//P8100/1C28.2 AOP1/B7/2014 ILT NRC R45 Given the following conditions:

- Unit 1 is at 100% power.

- 11 Main FRV has failed to control in AUTO.

- The crew has entered 1C28.2 AOP1, Feedwater Regulating Valve Control Failure - Unit 1.

- 11 Main FRV is in MANUAL.

- 11 Bypass FRV is in AUTO.

- 11 SG Narrow Range level is 36% and stable.

The Auxiliary Building Operator will throttle __________ the 11 Main FRV using the _________________________ to return 11 SG water level to program level.

A. OPEN HANDWHEEL B. OPEN MANUAL LOADING STATION C. CLOSED HANDWHEEL D. CLOSED MANUAL LOADING STATION 3-SPK Justifications:

a. Incorrect. Plausible as the MFRV will be opened; however, in this case use of the HW is prohibited and the MLS will be used.

b. Correct.

c. Incorrect. Plausible if examinee confuses PRZR band with SG band and incorrectly believes that SG level is high.

d. Incorrect. Plausible as the MLS will be used to control SGWL; however, in this case the MFRV will be opened vice closed.

Page 93

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

059 Main Feedwater 2.4.35:

Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Technical Reference(s): 1C28.2 AOP1 pgs. 3-4; B7 fig. B7-24 pg. 63 Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-006 Obj. 7A Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 94

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

46. P8180L-007 037/061 K1.03/3.5/3.9/5//P8100/B28B//2014 ILT NRC R46 The steam supply for the TD AFW pump is connected to _____________ Main Steam header(s), ______________ of the MSIV(s).

A. BOTH upstream B. BOTH downstream C. ONLY "A" upstream D. ONLY "B" downstream 1-F Justifications:

a. Correct.

b. Incorrect. Plausible as TDAFW pump steam supply comes from both SGs; however, the taps are located upstream of the MSIVs.

c. Incorrect. Plausible as the connections are upstream of the MSIVs; also if examinee incorrectly believes that only one header supplies steam to the turbine.

d. Incorrect. Plausible if examinee incorrectly believes only one header supplies steam to the turbine; also if examinee confuses the steam supplies joining downstream of the MVs with the supply connection upstream of the MSIVs.

Page 95

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

061 Auxiliary/Emergency Feedwater K1.03:

Knowledge of the physical connections and/or cause effect relationships between the AFW and the following systems:

Main steam system Technical Reference(s): B28B pg 11 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007 Obj. 5 Question Source: Bank # P8180L-007 037 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 4 55.43 Comments:

Page 96

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

47. P8186L-002 032/062 K2.01/3.3/3.4/7B//P8100/C20.3 AOP2/B20.5/2014 ILT NRC R47 Given the following conditions:

- Unit 1 and Unit 2 are at 100% power.

- The Spring Creek line is OOS.

- Unit 1 Generator locks out.

- 10 Bank transformer locks out.

- All AUTOMATIC actions are complete.

- NO operator actions are taken.

What is the status of Unit 1 and Unit 2 Reactor Coolant Pumps?

11 and 12 RCPs 21 and 22 RCPs A. NOT running NOT running B. NOT running running C. running NOT running D. running running 3-PEO Justifications:

a. Incorrect. Plausible as U1 N-S buses will de-energize; however, in this case U2 N-S buses remain energized.

b. Correct. 1R Transformer will lose power resulting in a loss of U1 N-S buses. U2 N-S buses remain unaffected.

c. Incorrect. Plausible if examinee incorrectly confuses U1 and U2 buses.

d. Incorrect. Plausible as the Unit 2 buses will remain energized; however, in this case the Unit 1 buses will de-energize due to loss of 1R transformer.

Page 97

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

062 A.C. Electrical Distribution K2.01:

Knowledge of bus power supplies to the following:

Major system loads Technical Reference(s): C20.3 AOP2 pg. 3; C47006-0107 1GT Lockout; C92000-PT46; fig. B20.2-1; B3 pg. 13 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-002 Obj. 7B Question Source: Bank # _P8186L-002 032_

Modified Bank # _______

New _________

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X __

10 CFR Part 55 Content:

55.41 __7 __

55.43 __ ___

Comments:

Page 98

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

48. P8186L-005 012/063 K3.02/3.5/3.7/5B//P8100/C20.9 AOP2//2014 ILT NRC R48 Given the following conditions:

- Unit 1 is in Mode 3.

- A loss of Train B DC occurs.

Bus 16 source and load breakers will...

A. AUTOMATICALLY trip OPEN.

B. transfer control power to Train A DC.

C. be MANUALLY operated locally at Bus 16.

D. be MANUALLY operated from the Control Room.

3-PEO Justification:

a. Incorrect. Plausible if examinee incorrectly believes the breakers will switch states and that the system response to loss of DC control power is similar to a loss of AC voltage.

b. Incorrect. Plausible as this is the correct system response for Non-safeguards busses 11 & 12.

c. Correct.

d. Incorrect. Plausible as breakers are normally operated from the CR; however, in this case without control power, breakers must be operated locally at the bus.

Page 99

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

063 D.C Electrical Distribution K3.02:

Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following:

Components using DC control power Technical Reference(s): 1C20.9 AOP2 pg. 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-005 Obj. 5B Question Source: Bank # _ _

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __ X __

Comprehension or Analysis __ __

10 CFR Part 55 Content:

55.41 __7 __

55.43 __ ___

Comments:

Page 100

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

49. P8186L-008 048/064 K4.11/3.5/4.0/3E//P8100/B18C//2014 ILT NRC R49 Given the following conditions:

- Unit 1 is at 100% power.

- Unit 1 Safety Injection actuates.

- NO operator actions are taken.

Will a load rejection/restoration occur on Bus 15 AND what is the status of D1 Emergency Diesel Generator?

BUS 15 LOAD REJECTION D1 EMERGENCY

& RESTORATION DIESEL GENERATOR A. YES RUNNING B. YES NOT RUNNING C. NO RUNNING D. NO NOT RUNNING 2-RI Justifications:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes D1 will not start unless power to Bus 15 is lost; also, in this case load rejection/restoration will occur.

c. Incorrect. Plausible if examinee incorrectly believes load rejection/restoration does not occur because power was not lost to Bus 15; however, in this case the load sequencer will reject and restore loads.

d. Incorrect. Plausible if examinee incorrectly believes load rejection/restoration does not occur and D1 does not start because power was not lost to Bus 15.

Page 101

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

064 Emergency Diesel Generators K4.11:

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

Automatic load sequencer: safeguards Technical Reference(s): B18C pg. 13 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-008 Obj. 3E Question Source: Bank # _ _

Modified Bank # _ __

New _X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __ X __

Comprehension or Analysis __ _

10 CFR Part 55 Content:

55.41 __8___

55.43 ____ _

Comments:

Page 102

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

50. P8182L-002 053/073 K5.01/2.5/3.0/3E//P8100/B18C//2014 ILT NRC R50 Given the following conditions:

- Safety Injection has ACTUATED on Unit 1.

1R-11, Unit 1 Containment Particulate Monitor, is _______________ Containment and 1R-12, Unit 1 Containment Gas Monitor, is _______________ Containment.

A. ISOLATED from ISOLATED from B. ISOLATED from ALIGNED to C. ALIGNED to ISOLATED from D. ALIGNED to ALIGNED to 2-RI Justifications:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes 1R-12 does not share the same flow path as 1R-11 and is not affected by SI.

c. Incorrect. Plausible if examinee incorrectly believes 1R-11 does not share the same flow path as 1R-12 and is not affected by SI.

d. Incorrect. Plausible if examinee incorrectly believes 1R-11 & 1R-12 are not affected by SI and CI; however, in this case the sample and return valves close on CI due to SI.

Page 103

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Process Radiation Monitoring K5.01:

Knowledge of the operational implications as they apply to concepts as they apply to the PRM system:

Radiation theory, including sources, types, units, and effects Technical Reference(s): B18C pg. 14 Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-002 Obj. 3E Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 11 55.43 Comments:

Page 104

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

51. P8182L-002 091/073 A4.03/3.1/3.2/3H//P8100/C21.1-5.1/PI-OPS-GFE-048L/2014 ILT NRC R51 Given the following conditions:

- The crew is testing R-18, Waste Liquid Disposal Liquid Effluent Monitor.

- R-18 background reading in step 5.4.2 is 300 CPM.

- The crew is on Step 5.4.5 of C21.1-5.1, 121 ADT Monitor Tank Release.

What is the R-18 Check Source reading minus background?

A. 1.8 x 102 B. 4.8 x 102 C. 5.7 x 103 D. 6.0 x 103 Page 105

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-SPK Justifications:

a. Incorrect. Plausible if examinee incorrectly uses narrow range values.

b. Incorrect. Plausible if examinee incorrectly uses only narrow range check source for final value.

c. Correct. 6.0 x 103 - 3 x 102 (6000-300) = 5.7 x 103

d. Incorrect. Plausible if examinee incorrectly uses only wide range check source for final value.

K/A Number:

Process Radiation Monitoring A4.03:

Ability to manually operate and/or monitor in the control room:

Check source for operability demonstration Technical Reference(s): C21.1-5.1 pg. 9; PI-OPS-GFE-048L pgs. 7-9.

Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-002 Obj. 3H Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 13 55.43 Comments:

Page 106

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

52. P8176L-003 071/076 A2.02/2.7/3.1/4B//P8100/C35 AOP2//2014 ILT NRC R52 Given the following conditions:

- Unit 1 and Unit 2 are at 100% power.

- D1 and D2 Diesel Generators are RUNNING.

- NO Safety Injection signal exists on either unit.

- Unit 1 and Unit 2 Non-Safeguards Buses are ENERGIZED.

- Loop A and Loop B Cooling Water Headers are SEPARATED.

- 11, 12, 21, and 22 Cooling Water pumps are RUNNING.

- The 121 Cooling Water pump is NOT RUNNING.

- Loop A Cooling Water Header pressure is 5 psig.

- Loop B Cooling Water Header pressure is 110 psig.

The crew will STOP ______ Emergency Diesel Generator(s) and TRIP __________.

A. D1 Unit 1 B. D2 Unit 2 C. D1 BOTH Units D. D2 Unit 1 2-RI Justifications:

a. Correct. Cooling water for D1 Diesel Generator and Unit 1 Turbine Building loads are supplied by Loop A. Cooling water for D2 Diesel Generator and Unit 2 Turbine Building loads are supplied by Loop B.

b. Incorrect. Plausible if examinee incorrectly believes that D2 and U2 are supplied by Loop A.

c. Incorrect. Plausible as D1 will be stopped and if examinee incorrectly believes both units turbine building loads are supplied by loop A; however, U1 Turbine Building loads are supplied by Loop A and U2 Turbine Building loads are supplied by Loop B.

d. Incorrect. Plausible as U1 will be tripped; however, only D1 is supplied by loop A.

Page 107

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

076 Service Water System A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Service water header pressure Technical Reference(s): C35 AOP2 pg. 7-10, & Fig. 1 Proposed references to be provided to applicants during examination: None Learning Objective: P8176L-003 Obj. 4B Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 108

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

53. P8178L-005 045/078 K1.03/3.3*/3.4*/3.E//P8100/FIGURE B18C-3//2014 ILT NRC R53 Given the following conditions:

- A Unit 1 Containment Isolation signal is present.

What additional signal will cause a DIRECT automatic isolation of Instrument Air to Containment?

A. RCS Low Tavg B. Safety Injection C. Containment Spray Actuation D. High-High Containment Pressure (>17 psig) 1-I Justifications:

a. Incorrect. Plausible as a RCS Low Tavg signal is an input to a Main Steam Isolation signal which would cause a isolation of instrument air to containment; however, there would also need to be a high steam flow signal and SI signal present.

b. Incorrect. Plausible as a SI signal is an input to a Main Steam Isolation signal which would cause a isolation of instrument air to containment; however, there would also need to be a high steam flow signal present.

c. Incorrect. Plausible as a containment pressure greater than 23 psig will actuate Containment Spray; however, this signal is NOT an input to isolate instrument air to containment. This is a common misconception.

d. Correct. A containment pressure greater than 17 psig will cause a Main Steam Line Isolation signal.

Since a Containment Isolation signal is already present, instrument air to containment would isolate.

Page 109

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

078 Instrument Air System (IAS)

K1.03:

Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems:

Containment Air Technical Reference(s): B18C Figure B18C-3 page 27 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 3E Question Source: Bank # P8178L-005 045 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 4 55.43 Comments:

Page 110

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

54. P8178L-005 049/078 2.4.47/4.2/4.2/7C//P8100/NF-39244/B34/2014 ILT NRC R54 Given the following conditions:

Question continued on next page.

Page 111

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

54. P8178L-005 049/078 2.4.47/4.2/4.2/7C//P8100/NF-39244/B34/2014 ILT NRC R54 Question continued from previous page.

Which valve will isolate the leak?

A. A B. B C. C D. D 3-SPR Justifications:

a. Correct. Unit 1 side air pressure being low and Unit 1 side air flow being high indicates the leak is on the Unit 1 side. Also Unit 2 air pressure and flow are close to normal. Valve A being closed would isolate the air leak.

b. Incorrect. Plausible if the leak location is diagnosed correctly, but incorrectly believe air flow from valve A side is automatically isolated and believes the check valve next to valve B is allowing backflow from Unit 2

c. Incorrect. Plausible if examinee misdiagnoses leak location is on the Unit 2 side, incorrectly believes air flow from valve D side is automatically isolated, and believes check valve next to valve C is allowing backflow from Unit 1.

d. Incorrect. Plausible if examinee misdiagnoses leak location is on the Unit 2 side.

Page 112

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

078 Instrument Air System (IAS) 2.4.47:

Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Technical Reference(s): NF-39244, B34 pg 19, P8178L-005 pg 44.

Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 7C Question Source: Bank # P8178L-005 049 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 4 55.43 Comments:

Page 113

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

55. P8180L-009F 006/103 A3.01/3.9/4.2/7B//P8100/B19//2014 ILT NRC R55 Given the following conditions:

- INITIALLY:

- Containment Isolation occurred.

- 11 and 12 Containment Vacuum Breakers operated as expected.

- NOW:

- Containment to Annulus D/P is as follows:

- 44104-A7, 11 CONTMT VAC BKR CLOSED, is NOT LIT.

- 44104-B7, 12 CONTMT VAC BKR CLOSED, is LIT.

What is the status of 11 and 12 Containment Vacuum Breakers?

11 CNTMT VAC BKR 12 CNTMT VAC BKR A. Failed to CLOSE Failed to OPEN B. Failed to CLOSE CLOSED as expected C. OPENED as expected Failed to OPEN D. OPENED as expected CLOSED as expected 3-SPK Justifications:

a. Incorrect. Plausible as 12 Vac Bkr failed to open; however, 11 Vac Bkr opened as expected.

b. Incorrect. Plausible if examinee does not know the correct setpoint and proper operation of the vacuum breakers.

c. Correct. Since DP is greater than negative .4, then both vacuum breakers will normally open.

d. Incorrect. Plausible as 11 Vac Bkr opened as expected; however, 12 Vac Bkr failed to open.

Page 114

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

103 Containment A3.01:

Ability to monitor automatic operation of the containment system, including:

Containment isolation Technical Reference(s): B19 pgs. 8-9 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009F Obj. 7B Question Source: Bank #: P8180L-009F 006 Modified Bank #:

New:

Question History: Last NRC Exam: N/A Question Cognitive Level:

Memory or Fundamental Knowledge:

Comprehension or Analysis: X 10 CFR Part 55 Content:

55.41: 9 55.43:

Comments:

Page 115

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

56. P8184L-005 035/001 A2.17/3.3/3.8/3J//P8100/1C5 AOP5//2014 ILT NRC R56 Given the following conditions:

- Unit 1 is at 80% power.

- Bank D Group Counter is at 200 steps.

- Bank D Rod K7 Rod Position Indication is at 187 steps.

- The crew is performing 1C5 AOP5, Misaligned Rod, Stuck Rod, and/or RPI Failure or Drift.

- The lift coils are disconnected for all Bank D Rods except for Rod K7.

- When Bank D is driven IN 15 steps, the following indications are noted:

- RCS Tavg remains constant.

- K7 Rod Position Indicator remains constant.

- Bank D Group Counter lowers 15 steps.

- When Bank D is driven OUT 15 steps, the following indications are noted:

- RCS Tavg remains constant.

- K7 Rod Position Indicator remains constant.

- Bank D Group Counter rises 15 steps.

What occurred to Rod K7?

A. The Rod is STUCK B. The Rod is MISALIGNED C. The Position Indicator is FAILED D. The Position Indicator has DRIFTED 3-SPK Justifications:

a. Correct.

b. Incorrect. Plausible if the examinee does not understand the difference between a misaligned and stuck rod.

c. Incorrect. Plausible as RPI indication staying constant is an indication of a failed RPI; however, RCS Tavg also was constant during rod movement. Therefore, the indications show a stuck rod.

d. Incorrect. Plausible as RPI indication staying constant is an indication of a drifted RPI; however, RCS Tavg also was constant during rod movement. Therefore, the indications show a stuck rod.

Page 116

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

001 Control Rod Drive System A2.17:

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

Rod-misalignment alarm Technical Reference(s): 1C5 AOP5 pages 6-8.

Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-005 Obj. 3J Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

10 CFR Part 55 Content:

55.41 __1 __

55.43 __ ___

Comments:

Page 117

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

57. P8184L-002 104/015 A3.04/3.3/3.5/11//P8100/SP 1005//2014 ILT NRC R57 Given the following conditons:

- A load change from 50% to 100% is temporarily suspended.

- SP 1005, NIS POWER RANGE DAILY CALIBRATION, is being performed.

- Reactor Thermal Power is 70.6%.

- Nuclear Instruments are reading as follows:

- N41 is 71.6%.

- N42 is 70.4%.

- N43 is 70.8%.

- N44 is 69.6%.

Which Nuclear Instrument(s) REQUIRE(s) a gain adjustment?

A. ONLY N41 B. ONLY N44 C. N41 AND N43 D. N42 AND N44 2-RI Justifications:

a. Incorrect. Plausible as N41 is reading greater than 0.5% of thermal power; however, since there is a load change in progress, NIS indicated power can be up to 2.0% greater than thermal power before a gain adjustment is required.

b. Incorrect. Plausible as N44 requires a gain adjustment; however, N42 also requires a gain adjustment.

c. Incorrect. Plausible if examinee incorrectly believes thermal power is required to be greater than NIS indicated power.

d. Correct. Per the precautions and limitations of SP 1005: If this surveillance procedure is performed during reduced power as a result of load follow operation, then, perform NIS gain adjustment if NIS indicated power is less than reactor thermal power or if NIS indicated power exceeds reactor thermal power by greater than 2%.

Page 118

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

015 Nuclear Instrumentation System A3.04:

Ability to monitor automatic operation of the NIS, including:

Maximum disagreement allowed between channels Technical Reference(s): SP 1005 page 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-002 Obj. 11 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 2 55.43 Comments:

Page 119

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

58. P8184L-003 042/016 A4.02/2.7/2.6*/4B//P8100/FIG C1-5//2014 ILT NRC R58 Given the following conditions:

What is reactor power?

A. 5%

B. 46%

C. 77%

D. 94%

Page 120

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-SPK Justifications:

a. Incorrect. Plausible if examinee incorrectly believes 557F is the lower limit for Tavg/Tref 0-100%.

b. Incorrect. Plausible if examinee incorrectly believes Tavg should be used to determine power; however, in this case Tref is used because it directly corresponds to reactor power whereas Tavg is low.

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes each degree Tref is less than 560 F equates to a 2% change in power.

K/A Number:

016 Non-Nuclear Instrumentation System A4.02:

Ability to manually operate and/or monitor in the control room:

Recorders Technical Reference(s): Figure C1-5 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-003 Obj. 4B Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 6 55.43 Comments:

Page 121

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

59. P8180L-001 032/028 K1.01/2.5/2.5/10A//P8100/C19.4/TS 3.6.4/2014 ILT NRC R59 Given the following conditions:

- Unit 1 is in Mode 1.

- Unit 1 Containment pressure is 1.8 psig.

- Unit 1 Containment depressuization is in progress per C19.4, Post LOCA Vent System - Depressurizing the Containment Vessel.

Technical Specification 3.6.4, Containment Pressure, is ____________ and the Post LOCA Vent System vents containment pressure to the ___________ Building.

A. MET Shield B. MET Auxiliary C. NOT MET Shield D. NOT MET Auxiliary 2-RI Justifications:

a. Correct.

b. Incorrect. Plausible as T.S. 3.6.4 is met; however, containment pressure is vented to the Shield Building when using Post LOCA Vent.

c. Incorrect. Plausible containment pressure is vented to the Shield Building when using Post LOCA Vent; however, T.S. 3.6.4 is met because containment pressure is lower than 2.0 psig.

d. Incorrect. Plausible if examinee incorrectly believes CTMT pressure needs only to be lowered <1.3 psig and incorrectly believes containment pressure is vented to the Auxiliary Building when using Post LOCA Vent.

Page 122

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

028 Hydrogen Recombiner and Purge Control System K1.01:

Knowledge of the physical connections and/or cause effect relationships between the HRPS and the following systems:

Containment annulus ventilation system (including pressure limits)

Technical Reference(s): C19.4 pgs. 3 & 7; T.S. 3.6.4 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-001 Obj. 10A Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 10 55.43 Comments:

Page 123

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

60. P8182L-004 021/033 2.1.28/4.1/4.1/3A//P8100/B16//2014 ILT NRC R60 The function of the Spent Fuel Pool Cooling Heat Exchangers is to transfer excess heat from the Spent Fuel Pool to the ______________________ System.

A. Cooling Water B. Component Cooling C. Residual Heat Removal D. Auxiliary Building Chilled Water 1-B Justifications:

a. Incorrect. Plausible if examinee incorrectly believes CLG WTR supplies the SPF HX; also because CLG WTR cools CC, which cools SFP HX but that is not the function of SFP HXs.

b. Correct.

c. Incorrect. Plausible as RHR cools the refueling cavity during refueling which can be connected to the SFP via transfer tube; however, the SFP HX transfers heat to CC.

d. Incorrect. Plausible as ABCW supplies multiple loads in CTMT and AB; however, CC supplies SFP HX.

Page 124

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Spent Fuel Cooling 2.1.28:

Knowledge of the purpose and function of major system components and controls.

Technical Reference(s): B16 pg. 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-004 Obj. 3A Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 125

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

61. P8180L-006 084/035 K3.02/4.0/4.3/7B//P8100/USAR 14.5.4.2//2014 ILT NRC R61 Given the following conditions:

- A Steam Generator Tube Rupture has occurred.

- NO operator actions have been taken.

Safety Injection will actuate on...

A. Low Steam Line Pressure.

B. Low Pressurizer Pressure.

C. High Containment Pressure.

D. Main Steam Line High Radiation 1-I Justifications:

a. Incorrect. Plausible if examinee incorrectly confuses plant response to SGTR with Faulted SG; Faulted SG will actuate SI signal on low steam pressure.

b. Correct.

c. Incorrect. Plausible if examinee incorrectly confuses plant response to SGTR with faulted SG; faulted SG will also actuate SI signal on high CTMT pressure.

d. Incorrect. Plausible because a SGTR will cause Main Steam Line Radiation to increase above the alarm setpoint; however, it by itself will not cause an SI actuation.

Page 126

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

035 Steam Generator (S/GS)

K3.02:

Knowledge of the effect that a loss or malfunction of the S/GS will have on the following:

ECCS Technical Reference(s): USAR 14.5.4.2.b pg. 14.5-14 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-006 Obj. 7B Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 127

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

62. P8176L-001 069/045 K4.13/2.6/2.8/4E//P8100/B22A//2014 ILT NRC R62 The Main Turbine Overspeed Protection Circuit (OPC) is set at _________ and when actuated will CLOSE ________________________ valves.

A. 103%

ONLY the Control and Intercept B. 103%

Stop, Reheat, Control and Intercept C. 109%

ONLY the Control and Intercept D. 109%

Stop, Reheat, Control and Intercept 1-I Justifications:

a. Correct.

b. Incorrect. Plausible as 103% is the correct setpoint for OPC; however, OPC closes only CVs & IVs.

c. Incorrect. Plausible as only CVs and IVs will close on OPC trip; however, the setpoint is 103%.

d. Incorrect. Plausible if examinee incorrectly confuses turbine ProTech overspeed setpoints and response with OPC.

Page 128

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

045 Main Turbine Generator (MT/G)

K4.13:

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

Overspeed protection Technical Reference(s): B22A pg. 23 Proposed references to be provided to applicants during examination: None Learning Objective: P8176L-001 Obj. 4E Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 129

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

63. PI-OPS-GFE-044L 002/072 K5.02/2.5/3.2/3//P8100/PI-OPS-GFE-044L//2014 ILT NRC R63 Given the following conditions:

- A 40 foot long horizontal pipe measures 200 mrem/hour at 1 foot.

- An Area Radiation Monitor is 20 feet away.

- Assume all measured radiation is from the pipe.

What is the Area Radiation Monitor reading?

A. 100 mrem/hour.

B. 10 mrem/hour.

C. 0.5 mrem/hour.

D. 0.025 mrem/hour.

3-SPK Justifications:

a. Incorrect. Plausible if examinee incorrectly uses L/2 and pipe length.

DR2 = 200 mrem/hr (20 ft / 40 ft) = 100 mrem/hr

b. Correct. Line Source equation out to L/2 distance (40 ft / 2) of 20 ft.

DR2 = DR1 (d1 / d2) = 200 mrem/hr (1 ft / 20 ft) = 10 mrem/hr

c. Incorrect. Plausible if examinee incorrectly uses point source equation.

DR2 = 200 mrem/hr (1 ft / 20 ft)2 = 0.5 mrem/hr

d. Incorrect. Plausible if examinee incorrectly uses point source equation and uses x3 function.

DR2 = 200 mrem/hr (1 ft / 20 ft)3 = 0.025 mrem/hr Page 130

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Area Radiation Monitoring K5.02:

Knowledge of the operational implications of the following concepts as they apply to the ARM system:

Radiation intensity changes with source distance Technical Reference(s): PI-OPS-GFE-044L pages 8-10 Proposed references to be provided to applicants during examination: None Learning Objective: PI-OPS-GFE-044L Obj. 3 Question Source: Bank # PI-OPS-GFE-044L 002 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 12 55.43 Comments:

Page 131

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

64. P8176L-003 054/075 K2.03/2.6*/2.7*/3B//P8100/C35//2014 ILT NRC R64 Given the following conditions:

- 22 Diesel Driven Cooling Water Pump has been declared INOPERABLE.

- 121 Cooling Water Pump is aligned as the safeguards pump replacement.

What is the power supply for 121 Cooling Water Pump?

A. Bus 15 B. Bus 16 C. Bus 25 D. Bus 26 1-F Justifications:

a. Incorrect. Plausible if examinee incorrectly believes 121 MDCLP supply Bus 27 is powered from Unit 1 SG buses; however, in this case Bus 27 is aligned to Bus 26.

b. Incorrect. Plausible if examinee incorrectly believes 121 MDCLP supply Bus 27 is powered from Unit 1 SG buses; however, in this case Bus 27 is aligned to Bus 26.

c. Incorrect. Plausible as Bus 27 is normally aligned to Bus 25 per 2C20.5 (SG bus aligned to 2RY);

however, in this case Bus 27 is aligned to Bus 26 due to inoperable Train B CLG WTR pump.

d. Correct.

Page 132

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

075 Circulating Water System K2.03:

Knowledge of bus power supplies to the following:

Emergency/essential SWS pumps Technical Reference(s): C35 pg. 51 Proposed references to be provided to applicants during examination: None Learning Objective: P8176L-003 Obj. 3B Question Source: Bank # P8176L-003 054 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 8 55.43 Comments:

Page 133

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

65. P8178L-002 024/086 A1.01/2.9/3.3/4I//P8100/B31/F5 APP K/2014 ILT NRC R65 Given the following conditions:

- A fire is reported in the Turbine Building.

- The crew has the following Control Board indications:

Fire Header Pressure is _________ the MINIMUM required pressure and the crew will ______________________.

A. below START 121 MD Fire Pump B. below STOP 121 Screenwash Pump C. above START 121 MD Fire Pump D. above STOP 121 Screenwash Pump Page 134

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-SPK Justifications:

a. Correct.

b. Incorrect. Plausible as the FH pressure is low; however in this case the SW pump would not be stopped.

c. Incorrect. Plausible as the MDFP will be started; however, the FH pressure is low.

d. Incorrect. Plausible if examinee incorrectly believes fire pressure is too high and the SW pump should be stopped; however, in this case pressure is too low, the SW pump will remain running, and the MDFP will be started.

K/A Number:

086 Fire Protection A1.01:

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

Fire header pressure Technical Reference(s): B31A pg. 9; F5 App K pg. 12; C31 pg. 10; C47022-0611 pg. 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-002 Obj. 4I Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 7 55.43 Comments:

Page 135

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

66. P8140L-201 007/2.1.3/3.7/3.9/1//P8100/SWI O-2//2014 ILT NRC R66 Given the following conditions:

- Unit 1 and Unit 2 are at 100% power.

- The crew has the minimum crew compliment for licensed operators.

- Both Lead ROs are in the Operator' s Lounge for a Pre-Job Brief.

- NO qualified relief is available for either Operator at the Controls.

- NO emergency situations exist.

What area from the picture above are BOTH Reactor Operators allowed?

A. A B. D C. E D. F Page 136

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 1-P Justifications:

a. Incorrect. Plausible as the Unit 1 RO is allowed in this area; however, the Unit 2 RO is NOT allowed in this area.

b. Correct. Per SWI O-2, this area is designated as Unit 1 and Unit 2 at the controls area.

c. Incorrect. Plausible as this area is a Unit 1 and Unit 2 Restrictive Area; however, there is a NOTE in SWI O-2 that prohibits either RO going into this area.

d. Incorrect. Plausible as the Unit 2 RO is allowed in this area; however, the Unit 1 RO is NOT allowed in this area.

K/A Number:

Conduct of Operations 2.1.3:

Knowledge of shift or short-term relief turnover practices.

Technical Reference(s): SWI O-2 pgs. 5 & 30.

Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-201 Obj. 1 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

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

55.41 10 55.43 Comments:

Page 137

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

67. PI-OPS-GFE-038L 020/2.1.18/3.6/3.8/5//P8100/FIG C1-8/SP 1669/2014 ILT NRC R67 Given the following conditions:

- Unit 1 is at 70% power.

- A 4% up-power was completed one hour ago.

- ERCS is OOS.

- Control Bank D Individual Rod Positions are as follows:

- G3 is at 100 steps

- C7 is at 105 steps

- G11 is at 112 steps

- K7 is at 113 steps

- Table 1 of ERCS Computer Out of Service Log has been filled out as follows:

- Figure C1-8 and T.S. LCO 3.1.4 are provided.

What is the status of the following limits?

Rod to Bank Deviation Rod Insertion Limits Limits of T.S. 3.1.4 A. MET MET B. MET NOT MET C. NOT MET MET D. NOT MET NOT MET Page 138

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR 3-SPR Justifications:

a. Incorrect. Plausible as the Rod to Bank Deviation Limits are met; however, Rod Insertion Limits are NOT met.

b. Incorrect. Plausible if examinee misinteprets Fig. C1-8 and believes Rod Insertion limits are MET.

c. Correct.

d. Incorrect. Plausible as Rod insertion limits are NOT met; however, Rod to Bank Deviation Limits are MET.

K/A Number:

Conduct of Operations 2.2.18:

Ability to make accurate, clear, and concise logs, records, status boards, and reports.

Technical Reference(s): Fig. C1-8; TS 3.1.4 Proposed references to be provided to applicants during examination: Fig. C1-8; and T.S. 3.1.4 pg. 1 Learning Objective: PI-OPS-GFE-038L Obj. 5 Question Source: Bank # _PI-OPS-GFE-038L 020__

Modified Bank # _ ______

New _______

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge _____

Comprehension or Analysis _X _

10 CFR Part 55 Content:

55.41 __6 55.43 _____

Comments:

Page 139

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

68. P8184L-002 070/2.1.40/2.8/3.9/10A//P8100/T.S. 3.9.3//2014 ILT NRC R68 Technical Specification 3.9.3, Refueling Operations - Nuclear Instrumentation, states _________ core subcritical neutron flux monitor(s) shall be OPERABLE and

_________ core subcritical neutron flux monitor audible count rate circuit(s) shall be OPERABLE.

A. ONE ONE B. ONE TWO C. TWO ONE D. TWO TWO 1-F Justifications:

a. Incorrect. Plausible as one audible count rate circuit is required; however, in this case TS requires two flux monitors. Also, if examinee incorrectly applies TS as the audible circuit can count towards the two flux monitors.

b. Incorrect. Plausible if examinee incorrectly applies TS and confuses which instrument requires 2 channels vice 1.

c. Correct.

d. Incorrect. Plausible if examinee incorrectly believes the two required flux monitors also applies to the audible count rate circuit.

Page 140

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Conduct of Operations 2.1.40:

Knowledge of refueling administrative requirements.

Technical Reference(s): T.S. 3.9.3 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-002 Obj. 10A Question Source: Bank # P8184L-002 070 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 10 55.43 Comments:

Page 141

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

69. P9150L-024 039/2.2.14/3.9/4.3/4//P8100/5AWI 3.10.1//2014 ILT NRC R69 Given the following conditions:

- Power Range Nuclear Instrument - N41 is failed LOW.

- The crew is removing N41 from service per 1C51.1, Instrument Failure Guide.

Which of the following is REQUIRED when tripping bistables?

A. Peer Check B. Self Check ONLY C. Concurrent Verification D. Independent Verification 1-P Justifications:

a. Incorrect. Plausible because it is a common misconception to confuse the requirements and differences between peer checks and concurrent verifications.

b. Incorrect. Plausible if examinee incorrectly believes self check only is sufficient for this operation; however, since the action involves tripping a bistable and could be a threat to plant reliability, a CV is required.

c. Correct.

d. Incorrect. Plausible if examinee confuses IV performance with CV performance. IV would allow the operator to trip B/S and then a second checker to verify the correct B/S was tripped. In this case, a CV is required to ensure the correct B/S is selected prior to tripping.

Page 142

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Equipment Control 2.2.14:

Knowledge of process for controlling equipment configuration or status.

Technical Reference(s): 5AWI 3.10.1 pg. 17; FP-PA-HU-02 pg. 30 Proposed references to be provided to applicants during examination: None Learning Objective: P9150L-024 Obj. 4 Question Source: Bank # _______

Modified Bank # _______

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __ ___

Comprehension or Analysis ___X _

10 CFR Part 55 Content:

55.41 __10__

55.43 _____

Comments:

Page 143

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

70. P8170L-001 020/2.2.40/3.4/4.7/10A//P8100/TS 3.4.1/PTLR, COLR/2014 ILT NRC R70 Given the following conditions:

- Unit 2 is at 100% power and steady state.

- RCS Tave is 562 °F.

- Pressurizer pressure is 2150 PSIG.

A Technical Specification entry will be made because...

A. RCS Tave is below minimum for criticality.

B. RCS Tave exceeds a reactor core safety limit.

C. pressurizer pressure is greater than a PTLR Limit.

D. pressurizer pressure is less than limit in the COLR.

2-DS Justifications:

a. Incorrect. Plausible because temp is out of normal band, but it is greater than 540°F.

b. Incorrect. Plausible because temp is higher than normal, but it is less than the safety limit of 564°F.

c. Incorrect. Plausible because pressure is out of normal band, but it is less than the PTLR limit.

d. Correct.

Page 144

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Equipment Control 2.2.40:

Ability to apply Technical Specifications for a system.

Technical Reference(s): T.S. 3.4.1 (3.4.2, 3.4.3, 2.1.1), PTLR page 3 , COLR page 7.

Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-001 Obj. 10A Question Source: Bank # P8170L-001 020 Modified Bank # ______________

New Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

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

55.41 10 55.43 Comments:

Page 145

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

71. P9130L-003 017/2.3.12/3.2/3.7/3//P8100/F2/CD 9.3/2014 ILT NRC R71 An area accessible to personnel that is determined to have a radiation level of 550 mRem per hour at 30 cm is classified as a...

A. Radiation Area B. High Radiation Area C. Very High Radiation Area D. Locked High Radiation Area 1-P Justifications:

a. Incorrect. Plausible if examinee incorrectly believes the limit for RA is >5 Rem.

b. Correct. (RA - >5mrem/hr; HRA - >100 mrem/hr; VHRA - >500 Rads/hr; LHRA - >1 Rem/hr)

c. Incorrect. Plausible if examinee confuses limits of HRA with VHRA of 500 Rads.

d. Incorrect. Plausible if examinee confuses limits of LHRA with HRA (100 mrem vs. 1000 mrem)

K/A Number:

Radiation Control 2.3.12:

Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Technical Reference(s): Fleet CD 9.3 pgs. 4-5 Proposed references to be provided to applicants during examination: None Learning Objective: P9130L-003 Obj. 3 Question Source: Bank # P9130L-003 017 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 12 55.43 Comments:

Page 146

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

72. P9130L-003 075/2.3.13/3.4/3.8/4G//P8100/CD 9.2/P9130L-003/2014 ILT NRC R72 Given the following conditions:

- An operator is required to complete a valve lineup in an area where the radiation level is 100 mrem/hour.

- The operator' s current year-to-date Total Effective Dose Equivalent (TEDE) is 1350 mrem.

What is the MAXIMUM amount of time the operator can work in this area and NOT exceed Prairie Island' s Administrative Dose Limit?

A. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months C. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 1-D Justifications:

a. Incorrect. Plausible if examinee incorrectly believes the site admin limit is the same as 450 mrem for pregnant workers; however, in this case the pregnant worker limit is total gestation period not one time dose.

b. Incorrect. Plausible if examinee incorrectly believes the site admin limit is 40% of the 15 R/yr LDE.

c. Correct. PI site admin limit is 2 Rem (40% of NRC 5 Rem/year limit).

d. Incorrect. Plausible if examinee incorrectly believes the site admin limit is the same as 10CFR20.1201 limits of 5 Rem/year.

Page 147

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Radiation Control 2.3.13:

Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Technical Reference(s): P9130L-003 pg. 16, CD 9.2 pages 5 & 6.

Proposed references to be provided to applicants during examination: None Learning Objective: P9130L-003 Obj. 4G Question Source: Bank # P9130L-003 075 Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level:

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

55.41 12 55.43 Comments:

Page 148

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

73. P8182L-002 088/2.3.15/2.9/3.1/7B//P8100/B11/1E-0/2014 ILT NRC R73 Which of the following radiation monitors can NOT be used to detect primary to secondary leakage?

A. 1R-7, U1 IN-CORE SEAL TABLE AREA R B. 1R-15, U1 CDSR AIR EJECT GAS RAD C. 1R-19, U1 SGBD BLOWDN LIQ R D. 1R-51, U1 MS A STM LINE RAD 1-B Justifications:

a. Correct.

b. Incorrect. Plausible if examinee incorrectly believes R7, R19, and R51 can be used to detect primary to secondary leakage; however, R7 cannot be used.

c. Incorrect. Plausible if examinee incorrectly believes R7, R15, and R51 can be used to detect primary to secondary leakage; however, R7 cannot be used.

d. Incorrect. Plausible if examinee incorrectly believes R7, R15, and R19 can be used to detect primary to secondary leakage; however, R7 cannot be used.

Page 149

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Radiation Control 2.3.15:

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Technical Reference(s): B11 pg. 15, 23, 24, 31.

Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-002 Obj. 7B Question Source: Bank # P8182L-002 088 Modified Bank #

New Question History: Last NRC Exam 2012 ILT NRC Exam Question Cognitive Level:

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

55.41 13 55.43 Comments:

Page 150

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

74. P8197L-010 027/2.4.5/3.7/4.3/2//P8100/P8197L-010//2014 ILT NRC R74 Given the following conditions:

- A 11 Steam Generator fault occurs in containment.

- The crew enters 1E-0, Reactor Trip or Safety Injection.

- The crew transitions to 1E-2, Faulted Steam Generator Isolation.

- 11 Steam Generator is isolated.

Which procedure will the crew enter NEXT?

A. 1E-1, Loss of Reactor or Secondary Coolant B. 1ES-0.2, Safety Injection Termination C. 1ES-1.2, Transfer to Recirculation D. 1ES-0.1, Reactor Trip Recovery 1-B Justifications:

a. Correct.

b. Incorrect. Plausible as SI Termination will occur; however, E-1 must be entered prior to ES-0.2.

c. Incorrect. Plausible if examinee incorrectly believes the RCS will lose sufficient inventory to warrant this transition; however, the only RCS loss is contraction due to cooldown.

d. Incorrect. Plausible if examinee incorrectly believes that a loss of secondary coolant has NOT occurred.

NOT SRO based on the fact the question can be answered by solely knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure.

Page 151

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Emergency Procedures/Plan 2.4.5:

Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

Technical Reference(s): 1E-2 pg. 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-010 Obj. 2 Question Source: Bank # _ _

Modified Bank # _ __

New __X_____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __X__

Comprehension or Analysis ___ _

10 CFR Part 55 Content:

55.41 __10___

55.43 ____ _

Comments:

Page 152

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR

75. P8197L-011 117/2.4.23/3.4/4.4/A1//P8100/SWI O-10/1ECA-0.0/2014 ILT NRC R75 Given the following conditions:

- Unit 1 is at 100% power.

- A loss of offsite power occurs.

- The crew is in 1ES-0.1, Reactor Trip Recovery.

- A lockout occurs on both Bus 15 and Bus 16.

- 'B'Pressurizer PORV fails OPEN.

- Critical Safety Function Status Tree shows a RED path for Heat Sink.

The NEXT procedure the crew will enter is...

A. 1FR-H.1, Response to Loss of Secondary Heat Sink.

B. 1E-1, Loss of Reactor or Secondary Coolant.

C. 1ECA-0.0, Loss of All Safeguards Power.

D. 1E-0, Reactor Trip or Safety Injection.

1-P Justifications:

a. Incorrect. Plausible as FR-H.1 will be entered after power is restored in ECA-0.0; however, in this case ECA-0.0 will be entered first.

b. Incorrect. Plausible as E-1 will be entered to address the PORV; however, in this case ECA-0.0 will be entered first followed by FR-H.1.

c. Correct.

d. Incorrect. Plausible as E-0 would be entered for the initial trip and again for the SI due to LOCA; however, ECA-0.0 must be entered first to restore power.

Page 153

2014 NRC INITIAL LICENSE WRITTEN EXAM REACTOR OPERATOR K/A Number:

Emergency Procedures/Plan 2.4.23:

Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

Technical Reference(s): SWI O-10 pgs. 11, 13, 1ECA-0.0 pg 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-011 Obj. A1 Question Source: Bank # _ _

Modified Bank # _ __

New __ X _____

Question History: Last NRC Exam ___N/A_________

Question Cognitive Level:

Memory or Fundamental Knowledge __X__

Comprehension or Analysis ___ _

10 CFR Part 55 Content:

55.41 __10__

55.43 ____ _

Comments:

You have completed the test!

Page 154

ML15126A554

Text

References:

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