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Initial Exam 2009-302 Draft RO Written Exam
	ML100670508
Person / Time
Site:	Turkey Point ; (DPR-031, DPR-041)
Issue date:	12/11/2009
From:	; NRC/RGN-II
To:	; Florida Power & Light Co
References
	50-250/09-302, 50-251/09-302 50-250/09-302, 50-251/09-302
	Download: ML100670508 (262)
	v • d • e

FACILITY NAME: Turkey Point REPORT NUMBER: 2009-302 Section 2 DRAFT RO WRITTEN EXAM CONTENTS:

gOraft RO Written Exam (75Q with ES-401-5 Information)

Location of Electronic Files: Submitted By: 1),),'1 rifw fl VerifiedBy 1J1J. J FACILITY NAME: Turkey Point REPORT NUMBER: 2009-302 Section 2 DRAFT RO WRITTEN EXAM CONTENTS:

gOraft RO Written Exam (75Q with ES-401-5 Information)

Location of Electronic Files: Submitted By: 1),),'1 rifw fl VerifiedBy 1J1J. J

Turkey Point Initial Licensed Examination List of references to be provided candidates during examination:

1. Steam tables 2. Tech Spec 3.3.1, Reactor Trip Instrumentation

3. Tech Spec 3.4.4, Relief Valves *

Turkey Point Initial Licensed Examination List of references to be provided candidates during examination:

1. Steam tables 2. Tech Spec 3.3.1, Reactor Trip Instrumentation

3. Tech Spec 3.4.4, Relief Valves *

3/4.3 INSTRUMENTATION

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3-1. ACTION: As shown in Table 3.3-1. SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation SUNeillance Requirement specified in Table 4.3-1. TURKEY POINT -UNITS 3 & 4 3/43-1 AMENDMENT NOS. 178 AND 172

3/4.3 INSTRUMENTATION

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3-1. ACTION: As shown in Table 3.3-1. SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation SUNeillance Requirement specified in Table 4.3-1. TURKEY POINT -UNITS 3 & 4 3/43-1 AMENDMENT NOS. 178 AND 172

* * -; TABLE 3.3-1 c ::0 /\ m REACTOR TRIP SYSTEM INSTRUMENTATION

-< -u 0 MINIMUM Z TOTAL NO. CHANNELS CHANNELS APPLICABLE

-; I FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION c Z 1. Manual Reactor Trip 2 1 2 1,2 1 =i (f) 2 1 U> 2 3*,4*, 5* 9 Qo 2. Power Range, Neutron Flux a. High Setpoint 4 2 3 1,2 2 b. Low Setpoint 4 2 3 1##, 2 2 3. Intermediate Range, Neutron Flux 2 1 2 1##,2 3 4. Source Range, Neutron Flux U> a. Startup 2 1 2 2# 4 b. Shutdown**

2 0 2 3,4,5 5 U> c. Shutdown 2 1 2 3*,4*, 5* 9 I I\.) 5. Overtemperature L1 T 3 2 2 1,2 13 >> 6. Overpower L1 T 3 2 2 1,2 13 s: m 7. Pressurizer Pressure-Low 3 2 2 6 z 0 (Above P-7) s: m z B. Pressurizer Pressure--High 3 2 2 1,2 6 -; z 0 9. Pressurizer Water Level--High 3 2 2 1 13 (f) (Above P-7) ....... 0 10. Reactor Coolant Flow--Low

>> z a. Single Loop (Above P-B) 3/100p 2/100p 2/100p 1 6 0 ....... b. Two Loops (Above P-7 3/100p 2/100p 2/100p 1 6 U> and below P-B) 01 * * * -; TABLE 3.3-1 c ::0 /\ m REACTOR TRIP SYSTEM INSTRUMENTATION

-< -u 0 MINIMUM Z TOTAL NO. CHANNELS CHANNELS APPLICABLE

-; I FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION c Z 1. Manual Reactor Trip 2 1 2 1,2 1 =i (f) 2 1 U> 2 3*,4*, 5* 9 Qo 2. Power Range, Neutron Flux a. High Setpoint 4 2 3 1,2 2 b. Low Setpoint 4 2 3 1##, 2 2 3. Intermediate Range, Neutron Flux 2 1 2 1##,2 3 4. Source Range, Neutron Flux U> a. Startup 2 1 2 2# 4 b. Shutdown**

2 0 2 3,4,5 5 U> c. Shutdown 2 1 2 3*,4*, 5* 9 I I\.) 5. Overtemperature L1 T 3 2 2 1,2 13 >> 6. Overpower L1 T 3 2 2 1,2 13 s: m 7. Pressurizer Pressure-Low 3 2 2 6 z 0 (Above P-7) s: m z B. Pressurizer Pressure--High 3 2 2 1,2 6 -; z 0 9. Pressurizer Water Level--High 3 2 2 1 13 (f) (Above P-7) ....... 0 10. Reactor Coolant Flow--Low

>> z a. Single Loop (Above P-B) 3/100p 2/100p 2/100p 1 6 0 ....... b. Two Loops (Above P-7 3/100p 2/100p 2/100p 1 6 U> and below P-B) 01

* * -I TABLE 3.3-1 (Continued) c ::0 A REACTOR TRIP SYSTEM INSTRUMENTATION m -< "1J MINIMUM 0 TOTAL NO. CHANNELS CHANNELS APPLICABLE z -I FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I c 11. Steam Generator Water 3/stm. gen. 2/stm. gen. 2/stm. gen. 1,2 6 z :::::j Level--Low-Low (f) tv Qo 12. Steam Generator Water Level--2 stm. gen. 1 stm. gen. 1 stm. gen. 1,2 6 .j>. Low Coincident With Steam/ level and level coin-level and Feedwater Flow Mismatch 2 stm./feed-cident with 2 stm./feed-water flow 1 stm ./feed-waterflow mismatch in water flow mismatch in each stm. gen. mismatch in same stm. gen. tv same stm. or 2 stm. gen. gen. level and 1 tv stm .Ifeedwater , tv flow mismatch in same stm. gen. >> 13. Undervoltage--4.16 KV Busses s:: 2/bus 1/bus on 2/bus 12 m A and B (Above P-7) both busses z 0 s:: 14. Underfrequency-Trip of Reactor 21bus 1 to trip 2/bus 11 m z Coolant Pump Breaker(s)

Open RCPs*** -I z (Above P-7) 0 (f) 15. Turbine Trip (Above P-7) ..... tv a. Autostop Oil Pressure 3 2 2 1 12 --.J b. Turbine Stop Valve Closure 2 2 2 1 12 >> z 0 tv N * * * -I TABLE 3.3-1 (Continued) c ::0 A REACTOR TRIP SYSTEM INSTRUMENTATION m -< "1J MINIMUM 0 TOTAL NO. CHANNELS CHANNELS APPLICABLE z -I FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I c 11. Steam Generator Water 3/stm. gen. 2/stm. gen. 2/stm. gen. 1,2 6 z :::::j Level--Low-Low (f) tv Qo 12. Steam Generator Water Level--2 stm. gen. 1 stm. gen. 1 stm. gen. 1,2 6 .j>. Low Coincident With Steam/ level and level coin-level and Feedwater Flow Mismatch 2 stm./feed-cident with 2 stm./feed-water flow 1 stm ./feed-waterflow mismatch in water flow mismatch in each stm. gen. mismatch in same stm. gen. tv same stm. or 2 stm. gen. gen. level and 1 tv stm .Ifeedwater , tv flow mismatch in same stm. gen. >> 13. Undervoltage--4.16 KV Busses s:: 2/bus 1/bus on 2/bus 12 m A and B (Above P-7) both busses z 0 s:: 14. Underfrequency-Trip of Reactor 21bus 1 to trip 2/bus 11 m z Coolant Pump Breaker(s)

Open RCPs*** -I z (Above P-7) 0 (f) 15 . Turbine Trip (Above P-7) ..... tv a. Autostop Oil Pressure 3 2 2 1 12 --.J b. Turbine Stop Valve Closure 2 2 2 1 12 >> z 0 tv N

*

TABLE 3.3-1 {Continued} -i C REACTOR TRIP SYSTEM INSTRUMENTATION

0 A m MINIMUM -< -u TOTAL NO. CHANNELS CHANNELS APPLICABLE 0 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Z -i I 16. Safety Injection Input c from ESF 2 2 1,2 8 z =i C/J 17. Reactor Trip System Interlocks

<.v Qo a. Intermediate Range Neutron Flux, P-6 2 2 2# 7 b. Low Power Reactor Trips Block, P-7 P-10 Input 4 2 3 7 or Turbine First 2 1 2 7 <.v Stage Pressure <.v Power Range Neutron .b. c. Flux, P-8 4 2 3 1 7 d. Power Range Neutron Flux, P-10 4 2 3 1,2 7 >> 18. Reactor Coolant Pump Breaker s: m Position Trip z 0 a. Above P-8 1 !breaker 1 1/breaker 1 11 s: b. Above P-7 and below P-8 1/breaker 2 1/breaker 1 11 m z -i 19. Reactor Trip Breakers 2 1 2 1,2 8, 10 z 0 2 1 2 3*,4*, 5* 9 C/J -...J 20. Automatic Trip and Interlock 2 1 2 1,2 8 co logic 2 1 2 3*,4*, 5* 9 >> z 0 ..... -...J N * *

TABLE 3.3-1 {Continued} -i C REACTOR TRIP SYSTEM INSTRUMENTATION

0 A m MINIMUM -< -u TOTAL NO. CHANNELS CHANNELS APPLICABLE 0 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Z -i I 16. Safety Injection Input c from ESF 2 2 1,2 8 z =i C/J 17. Reactor Trip System Interlocks

<.v Qo a. Intermediate Range Neutron Flux, P-6 2 2 2# 7 b. Low Power Reactor Trips Block, P-7 P-10 Input 4 2 3 7 or Turbine First 2 1 2 7 <.v Stage Pressure <.v Power Range Neutron .b. c. Flux, P-8 4 2 3 1 7 d. Power Range Neutron Flux, P-10 4 2 3 1,2 7 >> 18. Reactor Coolant Pump Breaker s: m Position Trip z 0 a. Above P-8 1 !breaker 1 1/breaker 1 11 s: b. Above P-7 and below P-8 1/breaker 2 1/breaker 1 11 m z -i 19. Reactor Trip Breakers 2 1 2 1,2 8, 10 z 0 2 1 2 3*,4*, 5* 9 C/J -...J 20. Automatic Trip and Interlock 2 1 2 1,2 8 co logic 2 1 2 3*,4*, 5* 9 >> z 0 ..... -...J N

* ** *** # ## TABLE 3.3-1 (Continued)

TABLE NOTATION When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

When the Reactor Trip System breakers are in the open position, one or both of the backup NIS instrumentation channels may be used to satisfy this requirement.

For backup NIS testing requirements, see Specification 3/4.3.3.3, ACCIDENT MONITORING.

Reactor Coolant Pump breaker A is tripped by underfrequency sensor UF-3A 1 (UF-4A 1) or UF-3B1 (UF-4B1).

Reactor Coolant Pump breakers Band C are tripped by underfrequency sensor UF-3A2(UF-4A2) or UF-3B2(UF-4B2).

Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint.

Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock)

Setpoint.

ACTION STATEMENTS ACTION 1 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ACTION 2 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored per Specification 4.2.4.2 . TURKEY POINT -UNITS 3 & 4 3/43-5 AMENDMENT NOS. 179 AND 173 * * ** *** # ## TABLE 3.3-1 (Continued)

TABLE NOTATION When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

When the Reactor Trip System breakers are in the open position, one or both of the backup NIS instrumentation channels may be used to satisfy this requirement.

For backup NIS testing requirements, see Specification 3/4.3.3.3, ACCIDENT MONITORING.

Reactor Coolant Pump breaker A is tripped by underfrequency sensor UF-3A 1 (UF-4A 1) or UF-3B1 (UF-4B1).

Reactor Coolant Pump breakers Band C are tripped by underfrequency sensor UF-3A2(UF-4A2) or UF-3B2(UF-4B2).

Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint.

Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock)

Setpoint.

ACTION STATEMENTS ACTION 1 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ACTION 2 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored per Specification 4.2.4.2 . TURKEY POINT -UNITS 3 & 4 3/43-5 AMENDMENT NOS. 179 AND 173

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 3 -With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: a. Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b. Above P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER. ACTION 4 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes. ACTION 5 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes and verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ACTION 7 -With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification

3.0.3. ACTION

8 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 9 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour. ACTION 10-With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 8. The breaker shall not be bypassed while one of the diverse trip features is inoperable, except for the time required for performing maintenance to restore the breaker to OPERABLE status. TURKEY POINT -UNITS 3 & 4 3/43-6 AMENDMENT NOS. 179 AND 173

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 3 -With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: a. Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b. Above P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER. ACTION 4 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes. ACTION 5 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes and verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ACTION 7 -With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification

3.0.3. ACTION

8 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 9 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour. ACTION 10-With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 8. The breaker shall not be bypassed while one of the diverse trip features is inoperable, except for the time required for performing maintenance to restore the breaker to OPERABLE status. TURKEY POINT -UNITS 3 & 4 3/43-6 AMENDMENT NOS. 179 AND 173 TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 11 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ACTION 12 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ACTUATION LOGIC TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I ACTION 13 -With the number of OPERABLE channels one less than the Total number of channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . For subsequent required DIGITAL CHANNEL OPERATIONAL TESTS the inoperable channel may be placed in bypass status for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . TURKEY POINT -UNITS 3 & 4 3/4 3-7 AMENDMENT NOS. 179 AND 173 TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 11 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ACTION 12 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ACTUATION LOGIC TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I ACTION 13 -With the number of OPERABLE channels one less than the Total number of channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . For subsequent required DIGITAL CHANNEL OPERATIONAL TESTS the inoperable channel may be placed in bypass status for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . TURKEY POINT -UNITS 3 & 4 3/4 3-7 AMENDMENT NOS. 179 AND 173

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES

LIMITING CONDITION FOR OPERATION 3.4.4 Both power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3. ACTION: a. With one or both PORVs inoperable because of excessive leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s);

otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . b. With one PORV inoperable due to causes other than excessive leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . c. With both PORVs inoperable due to causes other than excessive leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore at least one PORV to OPERABLE status or close each PORV's associated block valve and remove power from the block valve; with both block valves closed with power removed, restore at least one PORV to OPERABLE status within 30 days and restore power to its associated block valve; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . d. With one or both block valve(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve(s) to OPERABLE status or close the block valve(s) and remove power from the block valve(s);

otherwise, place its associated PORV in manual control within the next hour and be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Restore at least one block valve to OPERABLE status within 30 days if both block valves are inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . e. The provisions of Specification 3.0.4 are not applicable.

TURKEY POINT -UNITS 3 & 4 3/44-10 AMENDMENT NOS. 166 AND 160

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES

LIMITING CONDITION FOR OPERATION 3.4.4 Both power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3. ACTION: a. With one or both PORVs inoperable because of excessive leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s);

otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . b. With one PORV inoperable due to causes other than excessive leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . c. With both PORVs inoperable due to causes other than excessive leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore at least one PORV to OPERABLE status or close each PORV's associated block valve and remove power from the block valve; with both block valves closed with power removed, restore at least one PORV to OPERABLE status within 30 days and restore power to its associated block valve; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . d. With one or both block valve(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve(s) to OPERABLE status or close the block valve(s) and remove power from the block valve(s);

otherwise, place its associated PORV in manual control within the next hour and be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Restore at least one block valve to OPERABLE status within 30 days if both block valves are inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . e. The provisions of Specification 3.0.4 are not applicable.

TURKEY POINT -UNITS 3 & 4 3/44-10 AMENDMENT NOS. 166 AND 160 l I * *

Question #1 ES-401 Question 1 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

Technical Reference(s):

5613-M-3041 sheet 2 09/25/2006 6/25/2009 Form ES-401-5 RO SRO 1 --1 00BAA2.2O 3.4 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902109 Obi-B & 11 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 _5_ X l I * *

Question #1 ES-401 Question 1 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

Technical Reference(s):

5613-M-3041 sheet 2 09/25/2006 6/25/2009 Form ES-401-5 RO SRO 1 --1 00BAA2.2O 3.4 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902109 Obi-B & 11 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 _5_ X

*

06/2512009 Turkey Point ILC 25 NRC Examination Question 1

With Unit 3 initially at 100%, the unit trips on low Pressurizer pressure.

Pressurizer pressure has stabilized at 1385 psig.

The crew suspects that a PORV opened inadvertently and is now partially open.

PRT pressure is 35 psig. Which one of the following confirming indications could be expected if a PORV is partially open? PORV relief line temperature at _----"{..;:.1.L-)

__ and Pressurizer level __ -----'(>.::2:..<.)

__ (1) (2) A 587° increasing due to a loss of sub cooling B 58JDF decreasing due to a loss of inventory C 281°F increasing due to a loss of subcooling 0 281°F decreasing due to a loss of inventory Page I 0[200 * *

06/2512009 Turkey Point ILC 25 NRC Examination Question 1

With Unit 3 initially at 100%, the unit trips on low Pressurizer pressure.

Pressurizer pressure has stabilized at 1385 psig.

The crew suspects that a PORV opened inadvertently and is now partially open.

PRT pressure is 35 psig. Which one of the following confirming indications could be expected if a PORV is partially open? PORV relief line temperature at _----'{..=.1.L-)

__ and Pressurizer level __ ----:(\.::2:.L)

__ (1) (2) A 587° increasing due to a loss of sub cooling B 58JDF decreasing due to a loss of inventory C 281°F increasing due to a loss of subcooling 0 281°F decreasing due to a loss of inventory Page I 0[200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 1 KJ A 008AA2.20 Pressurizer vapor space accident Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:

The effect of an open PORV on code safety, based on observation of plant parameters

Reference:

5613-M-3041 sheet 2 History: New Correct answer: C A. Incorrect; 281 ° is correct temperature.

Plausible; common misconception

-Tsat for PZR pressure.

B. Incorrect; 281 ° is correct temperature and PZR level increasing due to loss of subcooling (TMI). Plausible; common misconception

-Tsat for PZR pressure and losing mass out PORV. C. Correct; 281°F is the saturation temperature for 50 psia and PZR will increase due to head void when subcooling lost. D. Incorrect; PZR level increasing due to loss of subcooling (TMI). Plausible; losing mass out PORV. Cognitive level: 3 Need to use steam table to determine temperature Provide steam tables as a reference Page 2 of200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 1 KJ A 008AA2.20 Pressurizer vapor space accident Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:

The effect of an open PORV on code safety, based on observation of plant parameters

Reference:

5613-M-3041 sheet 2 History: New Correct answer: C A. Incorrect; 281 ° is correct temperature.

Plausible; common misconception

-Tsat for PZR pressure.

B. Incorrect; 281 ° is correct temperature and PZR level increasing due to loss of subcooling (TMI). Plausible; common misconception

-Tsat for PZR pressure and losing mass out PORV. C. Correct; 281°F is the saturation temperature for 50 psia and PZR will increase due to head void when subcooling lost. D. Incorrect; PZR level increasing due to loss of subcooling (TMI). Plausible; losing mass out PORV. Cognitive level: 3 Need to use steam table to determine temperature Provide steam tables as a reference Page 2 of200

*

Question #2 ES-401 Question 2 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KiA # Importance Rating Proposed Question:

See attached Proposed Answer: D Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 009EG2.2.44 Steam Tables -for the above conditions, RCS pressure is 760 psig. The HHSI Pumps should start delivering flow around 1500 psig. Technical Reference( s): ...!.4--==E::...::O=P'--=E-.!-I'-'F:.....:O""'P::...-.:..12=/"""0=2/....:0.:::.,8

_________

_ (Attach if not previously provided)

BD-EOP-E-l FOP 05/15/08 (including version/revision number ERG Executive Volume RCP Trip p. 14 Rev. 2 Proposed references to be provided to applicants during examination:

Steam Tables Learning Objective:

6902327 Obi. 3 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 _5_ This is a substitute KiA. Original KiA was 009EG2.2.3

_X_ * *

Question #2 ES-401 Question 2 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KiA # Importance Rating Proposed Question:

See attached Proposed Answer: D Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 009EG2.2.44 Steam Tables -for the above conditions, RCS pressure is 760 psig. The HHSI Pumps should start delivering flow around 1500 psig. Technical Reference( s): ...!..4--!:E::..,::oO::...!P_-=E-!-I-'Fo.....:O:::..;P"--'-12=/..:::,0=2/..:::,0.:::.,8

_________

_ (Attach if not previously provided)

BD-EOP-E-l FOP 05/15/08 (including version/revision number ERG Executive Volume RCP Trip p. 14 Rev. 2 Proposed references to be provided to applicants during examination:

Steam Tables Learning Objective:

6902327 Obi. 3 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 _5_ This is a substitute KiA. Original KiA was 009EG2.2.3

_X_

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 2 The crew has just entered 4-EOP-E-l, Loss of Reactor or Secondary Coolant, in response to a small break LOCA.

Containment temperature is 220°F.

Only the 4A HHSI Pump is running.

MOY-4-843 A & B, HHSI to Cold Leg MOY, are both closed.

RCS Subcooling is 40°F. In accordance with 4-EOP-E-l, which of the following statements is correct concerning the RCPs? The RO should ... A trip the RCPs. This will minimize RCS mass loss. B trip the RCPs. This will reduce heat input into the RCS. C NOT trip the RCPs. The RCPs are needed for pressure control. D NOT trip the RCPs. The RCPs are helping provide RCS heat removal. Page 3 0[200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 2 The crew has just entered 4-EOP-E-l, Loss of Reactor or Secondary Coolant, in response to a small break LOCA.

Containment temperature is 220°F.

Only the 4A HHSI Pump is running.

MOY-4-843 A & B, HHSI to Cold Leg MOY, are both closed.

RCS Subcooling is 40°F. In accordance with 4-EOP-E-l, which of the following statements is correct concerning the RCPs? The RO should ... A trip the RCPs. This will minimize RCS mass loss. B trip the RCPs. This will reduce heat input into the RCS. C NOT trip the RCPs. The RCPs are needed for pressure control. D NOT trip the RCPs. The RCPs are helping provide RCS heat removal. Page 3 0[200

*

Question 2 KIA 009EG2.2.44 Small Break LOCA 06/25/2009 Turkey Point ILC 25 NRC Examination Ability to verify control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions NOTE: This is a substitute KIA

Reference:

4-EOP-E-l FOP BD-EOP-E-l FOP ERG Executive Volume RCP Trip p. 14 Steam Tables -for the above conditions, RCS pressure is 1000 psig. The HHSI Pumps should start delivering flow around 1500 psig. Question history: New Correct answer: D A Incorrect; per E-l FOP trip RCPs ifflowpath verified -no flow. Plausible; RCP sub cooling trip criteria met and reason is the correct one. B Incorrect; per E-1 FOP trip RCPs if flowpath verified -no flow. Plausible; RCP subcooling trip criteria met and reason is a common misconception.

C Incorrect; per Executive Volume, don't trip RCP without flowpath so RCPs can help provide core heat removal via break and S/Gs. Plausible; RCPs used for spray during post-LOCA cool down and depressurization.

D Correct per above discussion Cognitive level: 2 Need to determine RCS pressure and should have HHSI flow. Furthermore, that RCPs should not be tripped and why. Page 4 of200 * *

Question 2 KIA 009EG2.2.44 Small Break LOCA 06/25/2009 Turkey Point ILC 25 NRC Examination Ability to verify control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions NOTE: This is a substitute KIA

Reference:

4-EOP-E-l FOP BD-EOP-E-l FOP ERG Executive Volume RCP Trip p. 14 Steam Tables -for the above conditions, RCS pressure is 1000 psig. The HHSI Pumps should start delivering flow around 1500 psig. Question history: New Correct answer: D A Incorrect; per E-l FOP trip RCPs ifflowpath verified -no flow. Plausible; RCP sub cooling trip criteria met and reason is the correct one. B Incorrect; per E-1 FOP trip RCPs if flowpath verified -no flow. Plausible; RCP subcooling trip criteria met and reason is a common misconception.

C Incorrect; per Executive Volume, don't trip RCP without flowpath so RCPs can help provide core heat removal via break and S/Gs. Plausible; RCPs used for spray during post-LOCA cool down and depressurization.

D Correct per above discussion Cognitive level: 2 Need to determine RCS pressure and should have HHSI flow. Furthermore, that RCPs should not be tripped and why. Page 4 of200

*

Question #3 ES-401 Question 3 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 --011EG2.1.7 Tech n ical R eference( s): .::...3

________ _ (Attach if not previously provided.,L.)

________________

_ (including version/revision number _________________

_ Proposed references to be provided to applicants during examination:

.:...;N:..;:;o,:...;.n=e

__ _ Learning Objective:

6902321 Obi. 11 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 ....,;5=-_

55.43 5 X * *

Question #3 ES-401 Question 3 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 --011EG2.1.7 Tech n ical R eference( s): .::...3

________ _ (Attach if not previously provided.,L.)

________________

_ (including version/revision number _________________

_ Proposed references to be provided to applicants during examination:

.:...;N:..;:;o,:...;.n=e

__ _ Learning Objective:

6902321 Obi. 11 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 ....,;5=-_

55.43 5 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 3 Unit 3 has experienced a safety injection with the following indications:

Containment temperature is 225°F

RCS pressure is 1100 psig and lowering.

RCS Tcolds are 300°F and lowering.

Gammametrics NIs are at 8% and decreasing at 0.1 dpm.

Intermediate Range NIs are at 10.6 amps with a positive 0.1 dpm SUR. The crew is preparing to transition from 3-EOP-E-0, Reactor Trip or Safety Injection.

What procedure should be the crew transition to first? A 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition, on an Orange path. B 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition, on a Red path. C 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS on an Orange path. o 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS on a Red path. Page 5 0[200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 3 Unit 3 has experienced a safety injection with the following indications:

Containment temperature is 225°F

RCS pressure is 1100 psig and lowering.

RCS Tcolds are 300°F and lowering.

Gammametrics NIs are at 8% and decreasing at 0.1 dpm.

Intermediate Range NIs are at 10.6 amps with a positive 0.1 dpm SUR. The crew is preparing to transition from 3-EOP-E-0, Reactor Trip or Safety Injection.

What procedure should be the crew transition to first? A 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition, on an Orange path. B 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition, on a Red path. C 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS on an Orange path. o 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS on a Red path. Page 5 0[200

*

Question 3 KJA 011EG2.1.7 Large Break LOCA 06/25/2009 Turkey Point ILC 25 NRC Examination Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior and instrument interpretation.

Reference:

3-EOP-F-0 History: New Correct answer: D A Incorrect per reference.

Plausible; conditions for FR-P.l in stem. B Incorrect per reference.

Plausible; conditions for FR-P.l in stem. C Incorrect per reference.

Plausible; IR indications would require FR-S.l on orange path D Correct per reference.

Cognitive level: 2 Candidate has to determine procedure transition from conditions in stem. Page 6 0[200 * *

Question 3 KJA 011EG2.1.7 Large Break LOCA 06/25/2009 Turkey Point ILC 25 NRC Examination Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior and instrument interpretation.

Reference:

3-EOP-F-0 History: New Correct answer: D A Incorrect per reference.

Plausible; conditions for FR-P.l in stem. B Incorrect per reference.

Plausible; conditions for FR-P.l in stem. C Incorrect per reference.

Plausible; IR indications would require FR-S.l on orange path D Correct per reference.

Cognitive level: 2 Candidate has to determine procedure transition from conditions in stem. Page 6 0[200

Question #4 ES-401 Question 4 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 015AK3.04 Technical Reference(s):

_T..;..:...::.S;..:...

-=3-=-.4.:..;...-'-'1.c...;.1

______________

_ (Attach if not previously provided) 0-ADM-536 section 3.4.1 02/18/2009

(including version/revision number) 3-ARP-097.CR

p. 7704/28/2990

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902163 Obi. 7 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X

Question #4 ES-401 Question 4 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 015AK3.04 Technical Reference(s):

-.;..T.:..!:.S::..:.. . ...::3:.:....4.:..:. . ...:..1.:.....:1

______________

_ (Attach if not previously provided) 0-ADM-536 section 3.4.1 02/18/2009

(including version/revision number) 3-ARP-097.CR

p. 7704/28/2990

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902163 Obi. 7 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X 0612512009 Turkey Point ILC 25 NRC Examination

Question 4

Unit 3 is at 35% power.

The 3A RCP breaker has just tripped. What automatic or manual action will occur and what is the reason for this action? A The reactor will automatically trip. This is a DNB concern. B The crew will immediately trip the reactor. This is a DNB concern. C The reactor will automatically trip. This is a kw/ft concern. D The crew will immediately trip the reactor. This is a kw/ft concern. *

Page 7 0[200 0612512009 Turkey Point ILC 25 NRC Examination

Question 4

Unit 3 is at 35% power.

The 3A RCP breaker has just tripped. What automatic or manual action will occur and what is the reason for this action? A The reactor will automatically trip. This is a DNB concern. B The crew will immediately trip the reactor. This is a DNB concern. C The reactor will automatically trip. This is a kw/ft concern. D The crew will immediately trip the reactor. This is a kw/ft concern. *

Page 7 0[200

*

06/2512009 Turkey Point ILC 25 NRC Examination Question 4 KIA 015AK3.04 RCP Malfunctions Knowledge for the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of Flow): Reduction of power to below the steady state power-to-flow limit

Reference:

Tech Spec 3.4. 1.1 0-ADM-536 section 3.4.1 0-ARP-097.CR p77 Question history: New question Correct answer: B A Incorrect; the plant is below P-8 and will not automatically trip. Plausible; either the Candidate does not know P-8 setpoint or believes loss of one RCP will cause a reactor trip. B Correct; per reference ARP requires the crew to trip the reactor and per ADM-536 this is a DNB concern C Incorrect; Not a kw/ft concern. Plausible; Candidate can confuse DNB with kw/ft D Incorrect; Not a kw/ft concern. Plausible; Candidate can confuse DNB with kw/ft Cognitive level: 2 Candidate has to compare power with setpoint for P-8. Page 80[200 * *

06/2512009 Turkey Point ILC 25 NRC Examination Question 4 KIA 015AK3.04 RCP Malfunctions Knowledge for the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of Flow): Reduction of power to below the steady state power-to-flow limit

Reference:

Tech Spec 3.4. 1.1 0-ADM-536 section 3.4.1 0-ARP-097.CR p77 Question history: New question Correct answer: B A Incorrect; the plant is below P-8 and will not automatically trip. Plausible; either the Candidate does not know P-8 setpoint or believes loss of one RCP will cause a reactor trip. B Correct; per reference ARP requires the crew to trip the reactor and per ADM-536 this is a DNB concern C Incorrect; Not a kw/ft concern. Plausible; Candidate can confuse DNB with kw/ft D Incorrect; Not a kw/ft concern. Plausible; Candidate can confuse DNB with kw/ft Cognitive level: 2 Candidate has to compare power with setpoint for P-8. Page 80[200

*

Question #5 ES-401 Question 5 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 --1 --022AA2.02 2L .-rL Technical Reference( s):

________ _ (Attach if not previously provided)

_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6900234 Obi. 1 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 _5_ X * *

Question #5 ES-401 Question 5 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 --1 --022AA2.02 2L .-rL Technical Reference( s):

________ _ (Attach if not previously provided)

_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6900234 Obi. 1 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 _5_ X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 5

Unit 3 is at 100% power.

The crew is responding to a loss of charging flow.

The 3A Charging Pump is running with the following indications:

>-Charging flow and pressure are oscillating

>-The SNPO reports the 3A Charging Pump is running normally.

In accordance with 3-0NOP-047.1, Loss of Charging Flow in Modes 1 Through 4, which one of the following is the most likely cause of the above event? The 3A Charging Pump ... A is gas bound. B has low oil pressure.

C relief valve is cycling. D suction piping is leaking. Page 9 0[200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 5

Unit 3 is at 100% power.

The crew is responding to a loss of charging flow.

The 3A Charging Pump is running with the following indications:

>-Charging flow and pressure are oscillating

>-The SNPO reports the 3A Charging Pump is running normally.

In accordance with 3-0NOP-047.1, Loss of Charging Flow in Modes 1 Through 4, which one of the following is the most likely cause of the above event? The 3A Charging Pump ... A is gas bound. B has low oil pressure.

C relief valve is cycling. D suction piping is leaking. Page 9 0[200

06/2512009 Turkey Point ILC 25 NRC Examination Question 5 KIA 022AA2.02 Loss of Rx Coolant Makeup Ability to detennine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Charging pump problems

Reference:

3-0NOP-047.1 Question history: New Correct answer: C A Incorrect; lAW ONOP-047.1 would expect high vibrations on running pump and reduced charging flow. Plausible; gas bound would effect flow. B Incorrect; would expect high vibrations on running pump and flow would not recover. Plausible; bearing problems would effect flow. C Correct lAW above reference.

D Incorrect; would see low charging.

Plausible; would produce low flow. Cognitive level: 2 Need to detennine cause of failure.

Page 100[200

06/2512009 Turkey Point ILC 25 NRC Examination Question 5 KIA 022AA2.02 Loss of Rx Coolant Makeup Ability to detennine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Charging pump problems

Reference:

3-0NOP-047.1 Question history: New Correct answer: C A Incorrect; lAW ONOP-047.1 would expect high vibrations on running pump and reduced charging flow. Plausible; gas bound would effect flow. B Incorrect; would expect high vibrations on running pump and flow would not recover. Plausible; bearing problems would effect flow. C Correct lAW above reference.

D Incorrect; would see low charging.

Plausible; would produce low flow. Cognitive level: 2 Need to detennine cause of failure.

Page 100[200

Question #6 ES-401 Question 6 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

RO 1 1 025AK1.01 6/25/2009 Form ES-401-5 SRO Per the conditions given, RCS is intact and S/Gs are available.

4-0NOP-050 step 13 establishes feed to S/Gs. Step 14 checks CETs increasing.

If RCPs not available, step 19 verifies natural circulation.

RCPs are not available because of the loss of CCW. Technical Reference(s):

0-ADM-051 Fig. 1 03/10/09 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902210 Obi. 2 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 10 55.43 X *

Question #6 ES-401 Question 6 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

RO 1 1 025AK1.01 6/25/2009 Form ES-401-5 SRO Per the conditions given, RCS is intact and S/Gs are available.

4-0NOP-050 step 13 establishes feed to S/Gs. Step 14 checks CETs increasing.

If RCPs not available, step 19 verifies natural circulation.

RCPs are not available because of the loss of CCW. Technical Reference(s):

0-ADM-051 Fig. 1 03/10/09 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902210 Obi. 2 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 10 55.43 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 6 Initial conditions:

Unit 4 operated for 5 days after a refueling outage.

The crew has since shutdown and gone on RHR with the following conditions:

>-RCS pressure is 350 psig >-RCS temperature is 115°F >-Time since shutdown -150 hours Subsequently, RHR has been lost. In accordance with 0-ADM-051, Figure 1, Outage Risk Assessment and Control, Typical heat Up Rates wN essel Full, approximately how long will it be before the RCS reaches 200°F? Reference provided:

0-ADM-051, Figure 1 A 40 to 45 minutes B 55 to 60 minutes C 85 to 90 minutes D 185 to 190 minutes Page 11 of 200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 6 Initial conditions:

Unit 4 operated for 5 days after a refueling outage.

The crew has since shutdown and gone on RHR with the following conditions:

>-RCS pressure is 350 psig >-RCS temperature is 115°F >-Time since shutdown -150 hours Subsequently, RHR has been lost. In accordance with 0-ADM-051, Figure 1, Outage Risk Assessment and Control, Typical heat Up Rates wN essel Full, approximately how long will it be before the RCS reaches 200°F? Reference provided:

0-ADM-051, Figure 1 A 40 to 45 minutes B 55 to 60 minutes C 85 to 90 minutes D 185 to 190 minutes Page 11 of 200

*

Question 6 KIA 025AKl.Ol Loss of RHR System 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge ofthe operational implications of the following concepts as they apply to the Loss of Residual Heat Removal System: Loss ofRHRS during all modes of operation

Reference:

0-ADM-051 Figure 1 History: New Correct answer: B A Incorrect; correct answer is approximately 57 minutes. Plausible; ifuse wrong MWD, will get this answer B Correct lAW above reference.

C Incorrect; correct answer is approximately 57 minutes. Plausible; if misinterpret hours for days, could use 15 days instead of 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months . o Incorrect; correct answer is approximately 57 minutes. Plausible; if misinterpret hours for days, would use end of axis. Cognitive level: 3 Provide reference:

0-ADM-051, Figure 1 Page 12 of 200 * *

Question 6 KIA 025AKl.Ol Loss of RHR System 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge ofthe operational implications of the following concepts as they apply to the Loss of Residual Heat Removal System: Loss ofRHRS during all modes of operation

Reference:

0-ADM-051 Figure 1 History: New Correct answer: B A Incorrect; correct answer is approximately 57 minutes. Plausible; ifuse wrong MWD, will get this answer B Correct lAW above reference.

C Incorrect; correct answer is approximately 57 minutes. Plausible; if misinterpret hours for days, could use 15 days instead of 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months . o Incorrect; correct answer is approximately 57 minutes. Plausible; if misinterpret hours for days, would use end of axis. Cognitive level: 3 Provide reference:

0-ADM-051, Figure 1 Page 12 of 200 Question #7 ES-401 Question 7 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference(s):

4-0NOP-030 step 22 01/05/2009 6/25/2009 Form ES-401-5 RO SRO 1 1 026AA1.07 (Attach if not previously provided) 5614-M-3030 sheet 2 02/12/2990

(including versionlrevision number) ___________________

_

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902229 Obi. 4 & 7 (As available)

Question Source: Bank# 1.1.25.29.3.6 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x Question #7 ES-401 Question 7 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference(s):

4-0NOP-030 step 22 01/05/2009 6/25/2009 Form ES-401-5 RO SRO 1 1 026AA1.07 (Attach if not previously provided) 5614-M-3030 sheet 2 02/12/2990

(including versionlrevision number) ___________________

_

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902229 Obi. 4 & 7 (As available)

Question Source: Bank# Modified Bank # New 1.1.25.29.3.6

___ (Note changes or attach parent) Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x

.-Ulfemsin u G:'ITrnglApps\WE:MI\.1INE\PTN Exam\PTN Exam.xam Item: 1.1.25.29.3.6 69022290306;

leak of the Component Cooling Water piping in the Cask Wash Area has occurred, the leak has been isolated and CCW Head Tank level restored.

The plant is shutdown and will be cooled down to facilitate repairs. Which ONE of the following describes how the Charging/Letdown System is operated during the Cooldown?

A) Emergency cooling water will be aligned to all Charging pps to support inventory control during cooldown.

8) Letdown is isolated and the charging pump is operated as necessary to maintain PZR Level and RCP seal cooling. C) Seal injection flow MUST be maintained at all times to prevent overheating of the RCP seals. 0) Excess L TON is established, charging pumps are operated for inventory control and pressure control using aux. spray valve CV-311 Feedback for alternative A: 1.1.25.29.3.6 Attachment and set-up in field only provides capability (hoses) and guidance to hook up cooling to one pp at a time Feedback for alternative C: 1.1.25.29.3.6 incorrect for conditions given (leak location) rcp seal cooling should be available via thermal barrier cooling-in any case therre is no requirement to maintain continuous charging/seal injection Feedback for alternative 0: 1.1.25.29.3.6 Oistractor is not correct since normal L TON is isolated & procedures prohibit the use of aux. spray without Itdn

available Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

LOP, 026 AK3.03 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

8 Judging values of alternatives:

A=-1 8=1 C=-1 0=-1 Memo Field:

REFERENCE:

ONOP-030, Step 20 * .-Ulfemsin u G:'ITrnglApps\WE:MI\.1INE\PTN Exam\PTN Exam.xam Item: 1.1.25.29.3.6 69022290306;

leak of the Component Cooling Water piping in the Cask Wash Area has occurred, the leak has been isolated and CCW Head Tank level restored.

The plant is shutdown and will be cooled down to facilitate repairs. Which ONE of the following describes how the Charging/Letdown System is operated during the Cooldown?

A) Emergency cooling water will be aligned to all Charging pps to support inventory control during cooldown.

8) Letdown is isolated and the charging pump is operated as necessary to maintain PZR Level and RCP seal cooling. C) Seal injection flow MUST be maintained at all times to prevent overheating of the RCP seals. 0) Excess L TON is established, charging pumps are operated for inventory control and pressure control using aux. spray valve CV-311 Feedback for alternative A: 1.1.25.29.3.6 Attachment and set-up in field only provides capability (hoses) and guidance to hook up cooling to one pp at a time Feedback for alternative C: 1.1.25.29.3.6 incorrect for conditions given (leak location) rcp seal cooling should be available via thermal barrier cooling-in any case therre is no requirement to maintain continuous charging/seal injection Feedback for alternative 0: 1.1.25.29.3.6 Oistractor is not correct since normal L TON is isolated & procedures prohibit the use of aux. spray without Itdn

available Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

LOP, 026 AK3.03 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

8 Judging values of alternatives:

A=-1 8=1 C=-1 0=-1 Memo Field:

REFERENCE:

ONOP-030, Step 20 *

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 7

Unit 4 has experienced a CCW leak in the Cask Wash Area.

CCW has been isolated to the Charging Pumps.

The 4A Charging Pump is running In accordance with 4-0NOP-030, Component Cooling Water Malfunction, how will the Charging Pump(s) be operated during this event? The 4A Charging Pump will be __ (>..::1 ...... ) __ and Emergency Cooling Water will be aligned to (2) (1) (2) A run at max speed all Charging Pumps B run at max speed one Charging Pump C tripped all Charging Pumps D tripped one Charging Pump Page 13 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 7

Unit 4 has experienced a CCW leak in the Cask Wash Area.

CCW has been isolated to the Charging Pumps.

The 4A Charging Pump is running In accordance with 4-0NOP-030, Component Cooling Water Malfunction, how will the Charging Pump(s) be operated during this event? The 4A Charging Pump will be

__ and Emergency Cooling Water will be aligned to (2) (1) (2) A run at max speed all Charging Pumps B run at max speed one Charging Pump C tripped all Charging Pumps D tripped one Charging Pump Page 13 of 200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 7 KIA 026AAl.07 Loss of Component Cooling Water Ability to operate and 1 or monitor the following responses as they apply to the Loss of Component Cooling Water: Flow rates to the components and systems that are serviced by the CCWS; interactions among the components.

Reference:

4-0NOP-030 step 22 Drawing 5614-M-3030 sheet 2 History: EXAMINER question 1.1.25.29.3.6 modified Answer: B A. Incorrect; setup in field only provides capability to hook up cooling to one charging pump at a time. Plausible; candidate might not be aware of field arrangement.

B. Correct; run one pump at max speed and hook up service water to one pump. C. Incorrect; need to run one charging pump at max speed lAW Attachment in ONOP-030 and setup in field only provides capability to hook up cooling to one charging pump at a time. Plausible; candidate might not be aware of field arrangement.

D. Incorrect; need to run one charging pump at max speed lAW Attachment in ONOP-030 and setup in field only provides capability to hook up cooling to one charging pump at a time. Plausible; candidate might not be aware of field arrangement.

Cognitive level: 1 Page 14 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 7 KIA 026AAl.07 Loss of Component Cooling Water Ability to operate and 1 or monitor the following responses as they apply to the Loss of Component Cooling Water: Flow rates to the components and systems that are serviced by the CCWS; interactions among the components.

Reference:

4-0NOP-030 step 22 Drawing 5614-M-3030 sheet 2 History: EXAMINER question 1.1.25.29.3.6 modified Answer: B A. Incorrect; setup in field only provides capability to hook up cooling to one charging pump at a time. Plausible; candidate might not be aware of field arrangement.

B. Correct; run one pump at max speed and hook up service water to one pump. C. Incorrect; need to run one charging pump at max speed lAW Attachment in ONOP-030 and setup in field only provides capability to hook up cooling to one charging pump at a time. Plausible; candidate might not be aware of field arrangement.

D. Incorrect; need to run one charging pump at max speed lAW Attachment in ONOP-030 and setup in field only provides capability to hook up cooling to one charging pump at a time. Plausible; candidate might not be aware of field arrangement.

Cognitive level: 1 Page 14 of 200

*

Question #8 E8-401 Question 8 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form E8-401-5 RO SRO 1 --1 --027AK1.03 At 0% on PC-3-444J, heaters will be full on. This will increase liquid space temperature and increase Pressurizer pressure, driving up vapor space temperature.

Technical Reference(s):

__________

_ (Attach if not previously provided)

_________________

_ (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination:

Learning Objective:

6902912 Obi-1 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 8 X * *

Question #8 E8-401 Question 8 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form E8-401-5 RO SRO 1 --1 --027AK1.03 At 0% on PC-3-444J, heaters will be full on. This will increase liquid space temperature and increase Pressurizer pressure, driving up vapor space temperature.

Technical Reference(s):

.::::.5;:::..6..:....;1

__________

_ (Attach if not previously provided)

_________________

_ (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination:

Learning Objective:

6902912 Obi-1 (As available)

Question Source: Bank# Modified Bank # __ -:--(Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 8 X 06/25/2009 Turkey Point ILC 25 NRC Examination

Question 8

Unit 3 is stable at 70% power.

PC-3-444J, Pressurizer Pressure Controller, fails to 0% demand. How will the Pressurizer liquid and vapor space temperatures initially respond? Liquid space Vapor space A Increase Increase B Increase Decrease C Decrease Decrease D Decrease Increase *

Page 150[200 06/25/2009 Turkey Point ILC 25 NRC Examination

Question 8

Unit 3 is stable at 70% power.

PC-3-444J, Pressurizer Pressure Controller, fails to 0% demand. How will the Pressurizer liquid and vapor space temperatures initially respond? Liquid space Vapor space A Increase Increase B Increase Decrease C Decrease Decrease D Decrease Increase *

Page 150[200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 8 KIA 027 AKI.03 Pressurizer Pressure Control System Malfunction Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions:

Latent heat of vaporization/condensation

Reference:

561O-T-D-16B At 0% on PC-3-444J, heaters will be full on. This will increase liquid space temperature and increase Pressurizer pressure, driving up vapor space temperature.

History: New Correct answer: A A. Correct; 0% demand energizes heaters, which increases liquid space temperature and . . Increases pressunzer pressure.

B. Incorrect; both will increase due to heaters coming on. Plausible; need to realize 0% demand energizes heaters. C. Incorrect; both will increase due to heaters coming on. Plausible; need to realize 0% demand energizes heaters. D. Incorrect; both will increase due to heaters coming on. Plausible; need to realize 0% demand energizes heaters. Cognitive level: 2 Page 16 of 200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 8 KIA 027 AKI.03 Pressurizer Pressure Control System Malfunction Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions:

Latent heat of vaporization/condensation

Reference:

561O-T-D-16B At 0% on PC-3-444J, heaters will be full on. This will increase liquid space temperature and increase Pressurizer pressure, driving up vapor space temperature.

History: New Correct answer: A A. Correct; 0% demand energizes heaters, which increases liquid space temperature and . . Increases pressunzer pressure.

B. Incorrect; both will increase due to heaters coming on. Plausible; need to realize 0% demand energizes heaters. C. Incorrect; both will increase due to heaters coming on. Plausible; need to realize 0% demand energizes heaters. D. Incorrect; both will increase due to heaters coming on. Plausible; need to realize 0% demand energizes heaters. Cognitive level: 2 Page 16 of 200

Question #9 ES-401 Question 9 Written Examination Question Worksheet 6/25/2009 Form ES-401*5 Examination Outline Cross-

Reference:

Level Tier # Group # KJA# RO SRO 1 1 038EA2.08 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

With LOOP in stem of question, circulating water pumps have tripped off. Steam dumps to condenser are not available.

Letdown not in service -will use PORV. Technical Reference(s):

4-EOP-E-3 step 11 12/09/2008 (Attach if not previously provided) 5614-T -L 1 sheet 13 04/26/93 (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902339 Obi. 3 (As available)

Question Source: Bank# Modified Bank # New __ -:--(Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 X *

Question #9 ES-401 Question 9 Written Examination Question Worksheet 6/25/2009 Form ES-401*5 Examination Outline Cross-

Reference:

Level Tier # Group # KJA# RO SRO 1 1 038EA2.08 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

With LOOP in stem of question, circulating water pumps have tripped off. Steam dumps to condenser are not available.

Letdown not in service -will use PORV. Technical Reference(s):

4-EOP-E-3 step 11 12/09/2008 (Attach if not previously provided) 5614-T -L 1 sheet 13 04/26/93 (including version/revision number). ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902339 Obi. 3 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 X

*

06125/2009 Turkey Point ILC 25 NRC Examination Question 9

Unit 4 has experienced a Stearn Generator tube rupture.

Off-site power has been lost and will not be restored for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . In accordance with 4-EOP-E-3, Stearn Generator Tube Rupture, how will the RCS cooldown and depressurization to terminate safety injection be conducted?

The crew will use stearn dumps to ... A atmosphere and auxiliary spray. B atmosphere and a PORY. C condenser and auxiliary spray. D condenser and a PORV. Page 17 of 200 * *

06125/2009 Turkey Point ILC 25 NRC Examination Question 9

Unit 4 has experienced a Stearn Generator tube rupture.

Off-site power has been lost and will not be restored for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . In accordance with 4-EOP-E-3, Stearn Generator Tube Rupture, how will the RCS cooldown and depressurization to terminate safety injection be conducted?

The crew will use stearn dumps to ... A atmosphere and auxiliary spray. B atmosphere and a PORY. C condenser and auxiliary spray. D condenser and a PORV. Page 17 of 200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 9 KJ A 038EA2.08 Steam Gen. Tube Rupture Ability to detennine or interpret the following as they apply to a SGTR: Viable alternatives for placing plant in safe shutdown condition when condenser is not available

Reference:

5614-T-Ll sheet 13 4-EOP-E-3 With LOOP in stem of question, circulating water pumps have tripped off Steam dumps to condenser are not available.

Letdown not in service -will use PORV. History: New question Correct answer: B A. Incorrect; will use PORV. Plausible; letdown established later in E-3 and auxiliary spray is then available.

B. Correct; lAW with 4-EOP-E-3 C. Incorrect; SOTCs are not available due to loss of circulating water pumps and will use PORV. Plausible; SDTCs are the preferred method and letdown is established later in E-3 and auxiliary spray is then available.

D. Incorrect; SOTC are not available due to loss of circulating water pumps. Plausible; SOTCs are the preferred method. Cognitive level: 2 Candidate must diagnose that SOTCs not available due to LOOP and detennine method for depressurization.

Page 18 of 200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 9 KJ A 038EA2.08 Steam Gen. Tube Rupture Ability to detennine or interpret the following as they apply to a SGTR: Viable alternatives for placing plant in safe shutdown condition when condenser is not available

Reference:

5614-T-Ll sheet 13 4-EOP-E-3 With LOOP in stem of question, circulating water pumps have tripped off Steam dumps to condenser are not available.

Letdown not in service -will use PORV. History: New question Correct answer: B A. Incorrect; will use PORV. Plausible; letdown established later in E-3 and auxiliary spray is then available.

B. Correct; lAW with 4-EOP-E-3 C. Incorrect; SOTCs are not available due to loss of circulating water pumps and will use PORV. Plausible; SDTCs are the preferred method and letdown is established later in E-3 and auxiliary spray is then available.

D. Incorrect; SOTC are not available due to loss of circulating water pumps. Plausible; SOTCs are the preferred method. Cognitive level: 2 Candidate must diagnose that SOTCs not available due to LOOP and detennine method for depressurization.

Page 18 of 200

Question #10 ES-401 Question 10 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: D Explanation (Optional):

Technical Reference(s):

5613-M-3074 Sheet 3 04/09/2009 (Attach if not previously provided)

FSAR 14.1.11 & 14.2.504/98 RO 1 1 054AK1.01 6/25/2009 Form ES-401-5 SRO (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902914 Obi. 5 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _8_ 55.43 Used on Ginna NRC RO exam 2007 question 48 X *

Question #10 ES-401 Question 10 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: D Explanation (Optional):

Technical Reference(s):

5613-M-3074 Sheet 3 04/09/2009 (Attach if not previously provided)

FSAR 14.1.11 & 14.2.504/98 RO 1 1 054AK1.01 6/25/2009 Form ES-401-5 SRO (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902914 Obi. 5 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _8_ 55.43 Used on Ginna NRC RO exam 2007 question 48 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 10

Unit 4 was initially at 100% power.

A Feedline break developed at the piping connection to the 4A S/O inside Containment.

Which one of the following describes the effect of this event? A RCS temperatures lower prior to reactor trip. 4A S/O pressure stabilizes after Feedwater Isolation.

B RCS temperatures lower prior to reactor trip. 4A S/O pressure continues to depressurize after Feedwater Isolation.

C RCS temperatures rise prior to reactor trip. 4A S/O pressure stabilizes after Feedwater Isolation.

D RCS temperatures rise prior to reactor trip. 4A S/O pressure continues to depressurize after Feedwater Isolation.

Page 190[200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 10

Unit 4 was initially at 100% power.

A Feedline break developed at the piping connection to the 4A S/O inside Containment.

Which one of the following describes the effect of this event? A RCS temperatures lower prior to reactor trip. 4A S/O pressure stabilizes after Feedwater Isolation.

B RCS temperatures lower prior to reactor trip. 4A S/O pressure continues to depressurize after Feedwater Isolation.

C RCS temperatures rise prior to reactor trip. 4A S/O pressure stabilizes after Feedwater Isolation.

D RCS temperatures rise prior to reactor trip. 4A S/O pressure continues to depressurize after Feedwater Isolation.

Page 190[200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 10 KIA 054AK1.01 Loss of Main Feedwater Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater:

MFW line break depressurizes the S/G (similar to a steam line break)

Reference:

5613-M-3074 sheet 3 FSAR 14.1.11 & 14.2.5 Question history: Ginna NRC RO exam 2007 question 48 Correct answer: D A Incorrect; temperature would decrease if it were a steam break. A feed break will rob the S/G of water, causing it to heat up prior to the trip. No check valve keeping the S/G from depressurizing.

Plausible; this is the symptom of a steam line break downstream of MSIY. B Incorrect; temperature would decrease if it were a steam break. A feed break will rob the S/G of water, causing it to heat up prior to the trip. No check valve keeping the S/G from depressurizing.

Plausible; this is the symptom of a steam line break upstream of MSIV. C Incorrect; no check valve to keep S/G from depressurizing.

Plausible; ifleak were upstream of check valve, S/G would stabilize.

o Correct; A feed break will rob the S/G of water, causing it to heat up. No check valve keeping the S/G from depressurizing.

Cognitive level: 2 Candidate must diagnose effects of feed break on RCS temperature and S/G pressure Page 20 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 10 KIA 054AK1.01 Loss of Main Feedwater Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater:

MFW line break depressurizes the S/G (similar to a steam line break)

Reference:

5613-M-3074 sheet 3 FSAR 14.1.11 & 14.2.5 Question history: Ginna NRC RO exam 2007 question 48 Correct answer: D A Incorrect; temperature would decrease if it were a steam break. A feed break will rob the S/G of water, causing it to heat up prior to the trip. No check valve keeping the S/G from depressurizing.

Plausible; this is the symptom of a steam line break downstream of MSIY. B Incorrect; temperature would decrease if it were a steam break. A feed break will rob the S/G of water, causing it to heat up prior to the trip. No check valve keeping the S/G from depressurizing.

Plausible; this is the symptom of a steam line break upstream of MSIV. C Incorrect; no check valve to keep S/G from depressurizing.

Plausible; ifleak were upstream of check valve, S/G would stabilize.

o Correct; A feed break will rob the S/G of water, causing it to heat up. No check valve keeping the S/G from depressurizing.

Cognitive level: 2 Candidate must diagnose effects of feed break on RCS temperature and S/G pressure Page 20 of 200

Question #11 ES-401 Question 11 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

Technical Reference(s):

3-EOP-ECA-0.0 step 13 12/29/2008 RO 1 1 055EK3.02 (Attach if not previously provided)

BO-EOP-ECA-O.O step 1304/05/2009 6/25/2009 Form ES-401-5 SRO ----(including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902348 Obi. 6 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 10 55.43 X

Question #11 ES-401 Question 11 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

Technical Reference(s):

3-EOP-ECA-0.0 step 13 12/29/2008 RO 1 1 055EK3.02 (Attach if not previously provided)

BO-EOP-ECA-O.O step 1304/05/2009 6/25/2009 Form ES-401-5 SRO ----(including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902348 Obi. 6 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 10 55.43 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 11

Unit 3 has experienced a loss of all AC power.

The crew has detennined that a source of power is not available.

In accordance with 3-EOP-ECA-0.0, Loss of All AC Power, why are RCP Seal Manual Isolation Valves (3-297 AlBIC) and the RCP Seal Cooling Water Outlet Valve (MOV-3-626) closed? 3-297 AlBIC are closed to prevent (1) (2) A (1) thennal shocking the RCPs and MOV-3-626 is closed to prevent (2) steam introduction into the CCW System B (1) steam introduction into the RCP Seal Return (2) steam introduction into the CCW System C (1) steam introduction into the RCP Seal Return (2) thennal shocking the RCPs D (l) thennal shocking the RCPs (2) thennal shocking the RCPs Page 21 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 11

Unit 3 has experienced a loss of all AC power.

The crew has detennined that a source of power is not available.

In accordance with 3-EOP-ECA-0.0, Loss of All AC Power, why are RCP Seal Manual Isolation Valves (3-297 AlBIC) and the RCP Seal Cooling Water Outlet Valve (MOV-3-626) closed? 3-297 AlBIC are closed to prevent (1) (2) A (1) thennal shocking the RCPs and MOV-3-626 is closed to prevent (2) steam introduction into the CCW System B (1) steam introduction into the RCP Seal Return (2) steam introduction into the CCW System C (1) steam introduction into the RCP Seal Return (2) thennal shocking the RCPs D (l) thennal shocking the RCPs (2) thennal shocking the RCPs Page 21 of 200

*

Question 11 KIA 055EK3.02 Station Blackout 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge for the reasons for the following responses as they apply to the Station Blackout:

Actions contained in EOP for loss of offsite and onsite power

Reference:

3-EOP-ECA-0.0

& Basis Document for step 13 History: New question Correct answer: A A. Correct; per reference 297 AlBIC to prevent cold seal injection water thermal shocking the RCPs. MOV-3-626 is closed to prevent introduction of stearn into the main portion of CCW System B. Incorrect; 297 AlBIC not closed to prevent stearn introduction into RCP seal return lines. Plausible; Candidate could confuse reason for closing MOV-3-626 with reason for closing 297 AlBIC C. Incorrect; 297 AlBIC not closed to prevent stearn introduction into RCP seal return lines. Plausible; Candidate could confuse reason for closing MOV 626 with reason for closing 297 AlBIC D. Incorrect; MOV-3-626 not closed to prevent thermal shocking RCPs. Plausible; Candidate could confuse reason for closing MOV-3-626 with reason for closing 297 AlBIC Cognitive level: 1 Page 22 of 200 * *

Question 11 KIA 055EK3.02 Station Blackout 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge for the reasons for the following responses as they apply to the Station Blackout:

Actions contained in EOP for loss of offsite and onsite power

Reference:

3-EOP-ECA-0.0

& Basis Document for step 13 History: New question Correct answer: A A. Correct; per reference 297 AlBIC to prevent cold seal injection water thermal shocking the RCPs. MOV-3-626 is closed to prevent introduction of stearn into the main portion of CCW System B. Incorrect; 297 AlBIC not closed to prevent stearn introduction into RCP seal return lines. Plausible; Candidate could confuse reason for closing MOV-3-626 with reason for closing 297 AlBIC C. Incorrect; 297 AlBIC not closed to prevent stearn introduction into RCP seal return lines. Plausible; Candidate could confuse reason for closing MOV 626 with reason for closing 297 AlBIC D. Incorrect; MOV-3-626 not closed to prevent thermal shocking RCPs. Plausible; Candidate could confuse reason for closing MOV-3-626 with reason for closing 297 AlBIC Cognitive level: 1 Page 22 of 200

Question #12 ES-401 Question 12 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: D Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 056AG2.4.41 Technical Reference(s):

PTN EP section 3.1 -3.4 OS/20/2009 (Attach if not previously provided)

_________________

_ * (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

3202003 Obi. 4 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Know/edge Comprehension or Analysis 55.41 55.43 X

Question #12 ES-401 Question 12 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: D Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 056AG2.4.41 Technical Reference(s):

PTN EP section 3.1 -3.4 OS/20/2009 (Attach if not previously provided).

_________________

_ * (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

3202003 Obi. 4 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Know/edge Comprehension or Analysis 55.41 55.43 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 12

Unit 3 experienced a loss of off site power.

The 3A and 38 EDGs started and loaded their respective busses.

An Unusual Event was declared In accordance with the Turkey Point Radiological Emergency Plan, which one of the following is the emergency action level threshold that was met for this event? Events are in process or have occurred which ... A involve actual or likely major failures of plant functions needed for protection of the public. 8 involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.

C involve an actual or potential substantial degradation of the level of safety of the plant. D indicate a potential degradation of the level of safety of the plant. Page 23 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 12

Unit 3 experienced a loss of off site power.

The 3A and 38 EDGs started and loaded their respective busses.

An Unusual Event was declared In accordance with the Turkey Point Radiological Emergency Plan, which one of the following is the emergency action level threshold that was met for this event? Events are in process or have occurred which ... A involve actual or likely major failures of plant functions needed for protection of the public. 8 involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.

C involve an actual or potential substantial degradation of the level of safety of the plant. D indicate a potential degradation of the level of safety of the plant. Page 23 of 200

Question 12 KIA 056AG2.4.41 Loss of Off-site Power 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge of the emergency action level thresholds and classifications

Reference:

(PTN Radiological Emergency Plan) PTN EP sections 3.1 -3.4 History: New question Correct answer: D A. Incorrect; this is the definition for site are emergency.

Plausible; defines one of the EAL classifications.

B. Incorrect; this is the definition for general emergency.

Plausible; defines one of the EAL classifications.

C. Incorrect; this is the definition for an alert. Plausible; defines one of the EAL classifications.

D. Correct per above reference Cognitive level: 1

Page 24 of 200

Question 12 KIA 056AG2.4.41 Loss of Off-site Power 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge of the emergency action level thresholds and classifications

Reference:

(PTN Radiological Emergency Plan) PTN EP sections 3.1 -3.4 History: New question Correct answer: D A. Incorrect; this is the definition for site are emergency.

Plausible; defines one of the EAL classifications.

B. Incorrect; this is the definition for general emergency.

Plausible; defines one of the EAL classifications.

C. Incorrect; this is the definition for an alert. Plausible; defines one of the EAL classifications.

D. Correct per above reference Cognitive level: 1

Page 24 of 200

Question # 13 Question 13 ES-401 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

RO 1 1 057AA1.04 Technical Reference(s):

3-0NOP-003.7 Enclosure 1 06/27/2008 (Attach if not previously provided) 5613-M-3047 Sheet 204/04/2007 (including versionlrevision number) 5610-T 19 Sheet 1 10105/2006 Proposed references to be provided to applicants during examination:

None Learning Objective:

6902260 Obi. 4 (As available)

Question Source: Bank# 1.1.25.60.3.13 6/25/2009 Form ES-401-5 SRO Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam 1999 Q. 11 (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 Used on PTN NRC exam for ILC 18 RO question 11 x *

Question # 13 Question 13 ES-401 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

RO 1 1 057AA1.04 Technical Reference(s):

3-0NOP-003.7 Enclosure 1 06/27/2008 (Attach if not previously provided) 5613-M-3047 Sheet 204/04/2007 (including versionlrevision number) 5610-T 19 Sheet 1 10105/2006 Proposed references to be provided to applicants during examination:

None Learning Objective:

6902260 Obi. 4 (As available)

Question Source: Bank# 1.1.25.60.3.13 6/25/2009 Form ES-401-5 SRO Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam 1999 Q. 11 (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 Used on PTN NRC exam for ILC 18 RO question 11 x ttemsin 6:Yfmg\Apps\Wc:XAM1NC\P/N Exam\PTN Exam.xam Item: 1.1.25.60.3.13

.9022600313; Unit 3 is in Mode 3 with the following conditions:

A loss of a 120V Vital Instrument Panel has caused VCT level indicator U-3-115 to indicate zero level. Annunciator A 4/6 "VCT HIILO LEVEL" is in alarm. Which ONE of the following is correct for the given conditions?

VCT Auto Makeup: A) initiates and charging pump suction remains aligned to the VCT. 8) initiates and charging pump suction auto swaps to the RWST. C) is disabled and charging pump suction remains aligned to the VCT. D) is disabled and charging pump suction auto swaps to the RWST. CORRECT or INCORRECT feedback for item: 1.1.25.60.3.13

REFERENCES:

ONOP-003.7 Enclosure 1 page 1and SD-13 Figure 19 PTN Gp.18 RO Q#11 PTN Gp.18 SRO Q#16 NRC Level 2 Question NRC KA Importance:

(3.5/3.6)

Distractor Analysis:

a. Correct, with L T -115 failed on a loss of a vital bus ,auto makeup is initiated because it fails low but charging pump suction alignment remains the same because it takes 2/2 logic for the auto swap to the RWST. b. Plausible, VCT auto makeup does initiate but the required 2/2 logic is not made up for a swap of charging pump suction. The response is incorrect because the charging pump suction remains on the VCT. C. Plausible, if L T -115 failed high, VCT auto makeup would be disabled.

The charging pump suction would remain on the VCT. The response is incorrect because L T-115 fails low and makeup to the VCT is auto initiated.

d. Plausible, if L T -115 failed high, auto makeup would be disabled and this would also defeat the 2/2 logic for the auto swap of the charging pump suction. The response is wrong because both conditions given in the distractor do not occur. Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

LOP, NRC Exam Question, 057 AA1.04 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

A Judging values of alternatives:

A=1 8=-1 C=-1 D=-1 ttemsin 6:Yfmg\Apps\Wc:XAM1NC\P/N Exam\PTN Exam.xam Item: 1.1.25.60.3.13

.9022600313; Unit 3 is in Mode 3 with the following conditions:

A loss of a 120V Vital Instrument Panel has caused VCT level indicator U-3-115 to indicate zero level. Annunciator A 4/6 "VCT HIILO LEVEL" is in alarm. Which ONE of the following is correct for the given conditions?

VCT Auto Makeup: A) initiates and charging pump suction remains aligned to the VCT. 8) initiates and charging pump suction auto swaps to the RWST. C) is disabled and charging pump suction remains aligned to the VCT. D) is disabled and charging pump suction auto swaps to the RWST. CORRECT or INCORRECT feedback for item: 1.1.25.60.3.13

REFERENCES:

ONOP-003.7 Enclosure 1 page 1and SD-13 Figure 19 PTN Gp.18 RO Q#11 PTN Gp.18 SRO Q#16 NRC Level 2 Question NRC KA Importance:

(3.5/3.6)

Distractor Analysis:

a. Correct, with L T -115 failed on a loss of a vital bus ,auto makeup is initiated because it fails low but charging pump suction alignment remains the same because it takes 2/2 logic for the auto swap to the RWST. b. Plausible, VCT auto makeup does initiate but the required 2/2 logic is not made up for a swap of charging pump suction. The response is incorrect because the charging pump suction remains on the VCT. C. Plausible, if L T -115 failed high, VCT auto makeup would be disabled.

The charging pump suction would remain on the VCT. The response is incorrect because L T-115 fails low and makeup to the VCT is auto initiated.

d. Plausible, if L T -115 failed high, auto makeup would be disabled and this would also defeat the 2/2 logic for the auto swap of the charging pump suction. The response is wrong because both conditions given in the distractor do not occur. Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

LOP, NRC Exam Question, 057 AA1.04 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

A Judging values of alternatives:

A=1 8=-1 C=-1 D=-1 0612512009 Turkey Point ILC 25 NRC Examination

Question 13 Initial conditions:

45 gpm letdown orifice is in service.

Makeup is set for 75 gpm. Subsequently:

Unit 3 has lost 120 Volt Vital Instrument PaneI3-P07.

VCT level indicator LI-3-112 indicates 25%.

VCT level indicator LI-3-115 indicates zero level.

Annunciator A 4/6, VCT HULO LEVEL, is in alarm. Which of the following is correct for the given conditions?

VCT auto makeup ... A initiates and charging pump suction remains aligned to the VCT. B initiates and charging pump suction automatically swaps to the RWST. C is disabled and charging pump suction remains aligned to the VCT.

D is disabled and charging pump suction automatically swaps to the RWST.

Page 25 of 200 0612512009 Turkey Point ILC 25 NRC Examination

Question 13 Initial conditions:

45 gpm letdown orifice is in service.

Makeup is set for 75 gpm. Subsequently:

Unit 3 has lost 120 Volt Vital Instrument PaneI3-P07.

VCT level indicator LI-3-112 indicates 25%.

VCT level indicator LI-3-115 indicates zero level.

Annunciator A 4/6, VCT HULO LEVEL, is in alarm. Which of the following is correct for the given conditions?

VCT auto makeup ... A initiates and charging pump suction remains aligned to the VCT. B initiates and charging pump suction automatically swaps to the RWST. C is disabled and charging pump suction remains aligned to the VCT.

D is disabled and charging pump suction automatically swaps to the RWST.

Page 25 of 200

*

06125/2009 Turkey Point ILC 25 NRC Examination Question 13 KJA 057AAl.04 Loss of Vital AC Inst. Bus Ability to operate and 1 or monitor the following as they apply to the Loss of Vital AC Instrument Bus: R WST and VCT valves

Reference:

ONOP-003.7 Enclosure 1 5613-M-3047 sheet 2 5610-T -D-19 sheet 1 History: EXAMINER 1.1.25.60.3.13 Used on PTN NRC exam for ILC 18 RO question 11 Correct answer: A A. Correct; VCT LT-115 fails low on loss of3-P07, initiating auto makeup. Charging pump suction alignment remains the same because it takes a 212 logic for auto swap to RWST. B. Incorrect; auto swap to RWST does not occur. Plausible; VCT auto make initiates.

Candidate needs to know that swapover requires 2/2 logic C. Incorrect; VCT auto makeup will initiate.

Plausible; LT -115 failing high would disable auto makeup. Also, candidate might confuse L T -115 with L T -112, which does not cause auto makeup. D. Incorrect; VCT auto makeup will initiate.

Plausible; LT -115 failing high would disable auto makeup. Also, candidate might confuse LT-115 with LT-112, which does not cause auto makeup. Cognitive level: 2 Candidate needs to realize that swapover logic is 2/2 and L T -115 failing low causes auto makeup Page 26 of 200 * *

06125/2009 Turkey Point ILC 25 NRC Examination Question 13 KJA 057AAl.04 Loss of Vital AC Inst. Bus Ability to operate and 1 or monitor the following as they apply to the Loss of Vital AC Instrument Bus: R WST and VCT valves

Reference:

ONOP-003.7 Enclosure 1 5613-M-3047 sheet 2 5610-T -D-19 sheet 1 History: EXAMINER 1.1.25.60.3.13 Used on PTN NRC exam for ILC 18 RO question 11 Correct answer: A A. Correct; VCT LT-115 fails low on loss of3-P07, initiating auto makeup. Charging pump suction alignment remains the same because it takes a 212 logic for auto swap to RWST. B. Incorrect; auto swap to RWST does not occur. Plausible; VCT auto make initiates.

Candidate needs to know that swapover requires 2/2 logic C. Incorrect; VCT auto makeup will initiate.

Plausible; LT -115 failing high would disable auto makeup. Also, candidate might confuse L T -115 with L T -112, which does not cause auto makeup. D. Incorrect; VCT auto makeup will initiate.

Plausible; LT -115 failing high would disable auto makeup. Also, candidate might confuse LT-115 with LT-112, which does not cause auto makeup. Cognitive level: 2 Candidate needs to realize that swapover logic is 2/2 and L T -115 failing low causes auto makeup Page 26 of 200

Question #14 ES-401 Question 14 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 --1 --065AA1.01

...rL Following an extended loss of instrument air, attachment 2 will be used to open CV-3-2046A, 3A EDG level control valve. Unit 4 EDG makeup valves are electric and do not require instrument air to function.

Technical Reference(s):

0-ONOP-013 Attachment 2 03/21/2009 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X

Question #14 ES-401 Question 14 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 --1 --065AA1.01

...rL Following an extended loss of instrument air, attachment 2 will be used to open CV-3-2046A, 3A EDG level control valve. Unit 4 EDG makeup valves are electric and do not require instrument air to function.

Technical Reference(s):

0-ONOP-013 Attachment 2 03/21/2009 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 14

Turkey Point has experienced a long-term total loss of Instrument Air. In accordance with O-ONOP-013, how is CV-3-2046A, 3A EDG Level Control Valve, opened to fill the 3A EDG day tank? CV 2046A is opened using ... A a hand loader and a compressed air cylinder.

B normal level controller and a compressed air cylinder. C a hand loader and a compressed nitrogen cylinder.

D normal level controller and a compressed nitrogen cylinder.

Page 27 of 200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 14

Turkey Point has experienced a long-term total loss of Instrument Air. In accordance with O-ONOP-013, how is CV-3-2046A, 3A EDG Level Control Valve, opened to fill the 3A EDG day tank? CV 2046A is opened using ... A a hand loader and a compressed air cylinder.

B normal level controller and a compressed air cylinder. C a hand loader and a compressed nitrogen cylinder.

D normal level controller and a compressed nitrogen cylinder.

Page 27 of 200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 14 KJA 065AA1.01 Loss of Instrument Air Ability to operate and 1 or monitor the following as they apply to the Loss of Instrument Air: Remote manual loaders

Reference:

3-0NOP-013 Att. 2 Following an extended loss of instrument air, attachment 2 will be used to open CV 2046A, 3A EDG level control valve. Unit 4 EDG makeup valves are electric and do not require instrument air to function.

Question history: New Correct answer: C A Incorrect; a compressed nitrogen cylinder is use per reference, plausible because a hand loader is used per the reference to open the valve B Incorrect; 3A EDG requires instrument air for the normal level control to work. Plausible because normal level control will be functional on 4A EDG following an extended loss of instrument air C Correct per reference and discussion above. D Incorrect; 3A EDG requires instrument air for the normal level control to work. Plausible because normal level control will be functional on 4A EDG following an extended loss of instrument air and compressed nitrogen is used for 3A EDG. Cog level: 1 Page 280[200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 14 KJA 065AA1.01 Loss of Instrument Air Ability to operate and 1 or monitor the following as they apply to the Loss of Instrument Air: Remote manual loaders

Reference:

3-0NOP-013 Att. 2 Following an extended loss of instrument air, attachment 2 will be used to open CV 2046A, 3A EDG level control valve. Unit 4 EDG makeup valves are electric and do not require instrument air to function.

Question history: New Correct answer: C A Incorrect; a compressed nitrogen cylinder is use per reference, plausible because a hand loader is used per the reference to open the valve B Incorrect; 3A EDG requires instrument air for the normal level control to work. Plausible because normal level control will be functional on 4A EDG following an extended loss of instrument air C Correct per reference and discussion above. D Incorrect; 3A EDG requires instrument air for the normal level control to work. Plausible because normal level control will be functional on 4A EDG following an extended loss of instrument air and compressed nitrogen is used for 3A EDG. Cog level: 1 Page 280[200 Question #15 ES-401 Question 15 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

RO 1 1 WE04EK2.1 IfRCS pressure is increasing at step 3, go to E-1. If not, go to ECA-1.I, Loss of Emergency Coolant Recirculation.

Technical Reference(s):

3-EOP-ECA-1.2 step 3 12/29/2008 6/25/2009 Form ES-401-5 SRO --2JL (Attach if not previously provided)

__________________

_ (including versionlrevision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902333 Obi. 3 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 Used on H.B. Robinson 2007 exam question 53 X Question #15 ES-401 Question 15 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

RO 1 1 WE04EK2.1 IfRCS pressure is increasing at step 3, go to E-1. If not, go to ECA-1.I, Loss of Emergency Coolant Recirculation.

Technical Reference(s):

3-EOP-ECA-1.2 step 3 12/29/2008 6/25/2009 Form ES-401-5 SRO --2JL (Attach if not previously provided)

__________________

_ (including versionlrevision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902333 Obi. 3 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 Used on H.B. Robinson 2007 exam question 53 X 06/25/2009 Turkey Point ILC 25 NRC Examination

Question 15

A LOCA outside Containment has occurred.

The crew is performing 3-EOP-ECA-1.2, LOCA outside Containment.

Auxiliary Building radiation levels are lowering.

Safety Injection flow is 80 gpm and decreasing.

Pressurizer level is off scale low.

RCS pressure is 1450 psig and rising. In accordance with 3-EOP-ECA-l.2, what is the leak status? The leak is ... A isolated because RCS pressure is increasing.

B isolated because Auxiliary Building radiation levels are lowering.

C NOT isolated because SI pump flow still exists. D NOT isolated because Pressurizer level is not on scale. *

Page 29 of 200 06/25/2009 Turkey Point ILC 25 NRC Examination

Question 15

A LOCA outside Containment has occurred.

The crew is performing 3-EOP-ECA-1.2, LOCA outside Containment.

Auxiliary Building radiation levels are lowering.

Safety Injection flow is 80 gpm and decreasing.

Pressurizer level is off scale low.

RCS pressure is 1450 psig and rising. In accordance with 3-EOP-ECA-l.2, what is the leak status? The leak is ... A isolated because RCS pressure is increasing.

B isolated because Auxiliary Building radiation levels are lowering.

C NOT isolated because SI pump flow still exists. D NOT isolated because Pressurizer level is not on scale. *

Page 29 of 200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 15 KIA WE04EK2.1 LOCA Outside Containment Knowledge of the relationships between the (LOCA Outside Containment) and the following:

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features

Reference:

3-EOP-ECA-1.2 step 3 IfRCS pressure is increasing at step 3, go to E-l. If not, go to ECA-l.l, Loss of Emergency Coolant Recirculation.

History: H.B. Robinson 2007 exam question 53 Correct answer: A A. Correct IA W reference B. Incorrect; only parameter used in ECA-l.l is RCS pressure.

Plausible; leak isolation could cause Aux Bldg rad levels to lower. Could also be lowering because cleaner water coming out break injection flow. C. Incorrect; lAW reference pressure increase means leak isolated.

Plausible; with leak isolated pressure will increase, but pressure could still be low enough for HHSI flow with leak isolated.

D. Incorrect; lAW reference pressure increase means leak isolated.

Plausible; with leak isolated Pressurizer level will eventually come on scale Cognitive level: 1 Page 30 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 15 KIA WE04EK2.1 LOCA Outside Containment Knowledge of the relationships between the (LOCA Outside Containment) and the following:

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features

Reference:

3-EOP-ECA-1.2 step 3 IfRCS pressure is increasing at step 3, go to E-l. If not, go to ECA-l.l, Loss of Emergency Coolant Recirculation.

History: H.B. Robinson 2007 exam question 53 Correct answer: A A. Correct IA W reference B. Incorrect; only parameter used in ECA-l.l is RCS pressure.

Plausible; leak isolation could cause Aux Bldg rad levels to lower. Could also be lowering because cleaner water coming out break injection flow. C. Incorrect; lAW reference pressure increase means leak isolated.

Plausible; with leak isolated pressure will increase, but pressure could still be low enough for HHSI flow with leak isolated.

D. Incorrect; lAW reference pressure increase means leak isolated.

Plausible; with leak isolated Pressurizer level will eventually come on scale Cognitive level: 1 Page 30 of 200

Question # 16 ES-401 Question 16 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 WE05EK2.2 Technical Reference(s):

__________

_ (Attach if not previously provided) 5610-T-E-1591 Sheet 1 11/16/2006

(including versionlrevision number) ___________________

_

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902122 Obi. 9 (As available)

Question Source: Bank# 1.2.25.2.3.4 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detaifed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x

Question # 16 ES-401 Question 16 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 WE05EK2.2 Technical Reference(s):

...:..4-....:0::.:,N...:..O=..:-P--=0:...:.,7=5-=0=8::..::/2:..:0=/2:..:0'-=0=8

__________

_ (Attach if not previously provided) 5610-T-E-1591 Sheet 1 11/16/2006

(including versionlrevision number) ___________________

_

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902122 Obi. 9 (As available)

Question Source: Bank# 1.2.25.2.3.4 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detaifed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x

- +tems inG:\Trng'IApps\\NE7{AMtNE\PTNExam\PfNExarrf.-xcfm Item: 1.1.25.2.3.4

_69022020304; Given the following plant conditions:

Unit 3 is in Mode 3 The 38 SGFP is OOS The Unit 3 S/U Transformer Locks out The Auxiliary Feedwater System has failed completely, Which ONE of the following describes the order of priority established by ONOP-075, "Auxiliary Feedwater System Malfunction" for establishing feedwater flow from alternate sources? A) "A" S8SGFP, "8" S8SGFP, Unit's 2 OR Unit 4 8) "A" S8SGFP, "8" S8SGFP, 3C Condensate pump C) "8" S8SGFP, "A" S8SGFP, Unit's 2 OR Unit 4 0) "8" S8SGFP, "A" S8SGFP, 3C condensate pump Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

NLO, E05 EA2.2, NLOCT, SNPO Item Nonselectable

tem weight: 10 oints required for mastery: 1 Correct alternative(s):

C Judging values of alternatives:

A=-1 8=-1 C=1 0=-1 Memo Field:

REFERENCE:

ONOP-75 OL: 300 **+tems inG:\Trng'IApps\\NE7{AMtNE\PTNExam\PfNExarrf.-xcfm Item: 1.1.25.2.3.4

_69022020304; Given the following plant conditions:

Unit 3 is in Mode 3 The 38 SGFP is OOS The Unit 3 S/U Transformer Locks out The Auxiliary Feedwater System has failed completely, Which ONE of the following describes the order of priority established by ONOP-075, "Auxiliary Feedwater System Malfunction" for establishing feedwater flow from alternate sources? A) "A" S8SGFP, "8" S8SGFP, Unit's 2 OR Unit 4 8) "A" S8SGFP, "8" S8SGFP, 3C Condensate pump C) "8" S8SGFP, "A" S8SGFP, Unit's 2 OR Unit 4 0) "8" S8SGFP, "A" S8SGFP, 3C condensate pump Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

NLO, E05 EA2.2, NLOCT, SNPO Item Nonselectable

tem weight: 10 oints required for mastery: 1 Correct alternative(s):

C Judging values of alternatives:

A=-1 8=-1 C=1 0=-1 Memo Field:

REFERENCE:

ONOP-75 OL: 300

06125/2009 Turkey Point ILC 25 NRC Examination Question 16 Initial conditions:

Unit 3 is in Mode 3.

The 3B Steam Generator Feedpump is out of service. Subsequently:

The Unit 3 Startup Transformer locks out.

The Auxiliary Feedwater System has failed completely.

Main Feedwater is not available.

In accordance with 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink, what is the availability of the Standby Steam Generator Feedpumps (SSGFPs)? A A SSGFP available B SSGFP available B A SSGFP NOT available B SSGFP available C A SSGFP available B SSGFP NOT available

0 A SSGFP NOT available B SSGFP NOT available

Page 31 of 200

06125/2009 Turkey Point ILC 25 NRC Examination Question 16 Initial conditions:

Unit 3 is in Mode 3.

The 3B Steam Generator Feedpump is out of service. Subsequently:

The Unit 3 Startup Transformer locks out.

The Auxiliary Feedwater System has failed completely.

Main Feedwater is not available.

In accordance with 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink, what is the availability of the Standby Steam Generator Feedpumps (SSGFPs)? A A SSGFP available B SSGFP available B A SSGFP NOT available B SSGFP available C A SSGFP available B SSGFP NOT available

0 A SSGFP NOT available B SSGFP NOT available

Page 31 of 200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 16 KIA WE05EK2.2 Inadequate Heat Transfer -Loss of Secondary Heat Sink Knowledge of the relationships between the (Inadequate Heat Transfer -Loss of Secondary Heat Sink) and the following:

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

Reference:

4-0NOP-075 561O-T-E 1591 sheet 1 History: EXAMINER 1.1.25.2.3.4 significantly modified Correct answer: A A Correct; A SSGFP is from 3C 4kV bus, B SBSGFP is diesel B Incorrect; A SSGFP is powered from the 3C 4kV bus. Plausible; need to know power supply for A SSGFP and it would not be available if switchyard lost. C Incorrect; B SSGFP is diesel powered. Plausible; needs to know B SGFP is diesel powered. o Incorrect; A SSGFP is powered from the 3C 4kV bus and B SBSGFP is diesel powered. Plausible; need to know power supplies.

Cognitive level: 1 Page 32 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 16 KIA WE05EK2.2 Inadequate Heat Transfer -Loss of Secondary Heat Sink Knowledge of the relationships between the (Inadequate Heat Transfer -Loss of Secondary Heat Sink) and the following:

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

Reference:

4-0NOP-075 561O-T-E 1591 sheet 1 History: EXAMINER 1.1.25.2.3.4 significantly modified Correct answer: A A Correct; A SSGFP is from 3C 4kV bus, B SBSGFP is diesel B Incorrect; A SSGFP is powered from the 3C 4kV bus. Plausible; need to know power supply for A SSGFP and it would not be available if switchyard lost. C Incorrect; B SSGFP is diesel powered. Plausible; needs to know B SGFP is diesel powered. o Incorrect; A SSGFP is powered from the 3C 4kV bus and B SBSGFP is diesel powered. Plausible; need to know power supplies.

Cognitive level: 1 Page 32 of 200

*

Question #17 ES-401 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KIA # Question 17 Proposed Question:

See attached Proposed Answer: Explanation (Optional):

Importance Rating B RO 1 1 WE11EK3.1 6/25/2009 Form ES-401-5 SRO ECA-1.1 step 31 stops HHSI, RHR, & CSPs due to lack of NPSH. Charging left running -can maintain NPSH down to 20,000 gallons. Technical Reference(s):

3-EOP-ECA-1.1 step 1 RNO & step 3308/25/2008 (Attach if not previously provided)

BO-ECA-1.1 for above steps 8/25/2008 (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902332 Obi. 3 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 X *

Question #17 ES-401 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KIA # Question 17 Proposed Question:

See attached Proposed Answer: Explanation (Optional):

Importance Rating B RO 1 1 WE11EK3.1 6/25/2009 Form ES-401-5 SRO ECA-1.1 step 31 stops HHSI, RHR, & CSPs due to lack of NPSH. Charging left running -can maintain NPSH down to 20,000 gallons. Technical Reference(s):

3-EOP-ECA-1.1 step 1 RNO & step 3308/25/2008 (Attach if not previously provided)

BO-ECA-1.1 for above steps 8/25/2008 (including version/revision number) __________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902332 Obi. 3 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 17

Unit 3 has experienced a loss of emergency coolant recirculation.

RWST level is 59,000 gallons. In accordance with 3-EOP-ECA-l.l, Loss of Emergency Coolant Recirculation, what action should the crew take and why should they take that action? Immediately stop ... A all pumps taking suction from the RWST. There is insufficient suction head to run any pumps. B all pumps taking suction from the RWST except the Charging Pumps. There is insufficient suction head to run any pumps except the Charging Pumps. C only the RHR and Containment Spray Pumps. This will extend the availability of the R WST. D only the Charging Pumps and Containment Spray Pumps. This will extend the availability of the RWST. Page 33 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 17

Unit 3 has experienced a loss of emergency coolant recirculation.

RWST level is 59,000 gallons. In accordance with 3-EOP-ECA-l.l, Loss of Emergency Coolant Recirculation, what action should the crew take and why should they take that action? Immediately stop ... A all pumps taking suction from the RWST. There is insufficient suction head to run any pumps. B all pumps taking suction from the RWST except the Charging Pumps. There is insufficient suction head to run any pumps except the Charging Pumps. C only the RHR and Containment Spray Pumps. This will extend the availability of the R WST. D only the Charging Pumps and Containment Spray Pumps. This will extend the availability of the RWST. Page 33 of 200

*

06/2512009 Turkey Point ILC 25 NRC Examination Question 17 KIA WE 11 EK3.1 Loss of Emergency Coolant Recirculation Knowledge for the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation):

Facility operating characteristics during transient conditions, including chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.

Reference:

3-EOP-ECA-l.l step 1 RNO and step 31 -stop HHSI, RHR, & CSP BD-EOP-ECA-1.1 for above steps -pumps stopped for lack ofNPSH -Charging Pump can go to 20K History: New Correct answer: B A Incorrect; don't stop the Charging Pumps. Plausible; stop all pumps except Charging Pumps and reason is correct. B Correct lAW above discussion.

C Incorrect; also stop the HHSI Pumps. Plausible; want to extend availability ofRWST and HHSI Pumps would still provide core cooling. D Incorrect; don't stop the Charging Pump. Plausible; want to extend availability of R WST and HHSVRHR Pumps would still provide core cooling. Cognitive level: 1 Page 34 of 200 * *

06/2512009 Turkey Point ILC 25 NRC Examination Question 17 KIA WE 11 EK3.1 Loss of Emergency Coolant Recirculation Knowledge for the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation):

Facility operating characteristics during transient conditions, including chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.

Reference:

3-EOP-ECA-l.l step 1 RNO and step 31 -stop HHSI, RHR, & CSP BD-EOP-ECA-1.1 for above steps -pumps stopped for lack ofNPSH -Charging Pump can go to 20K History: New Correct answer: B A Incorrect; don't stop the Charging Pumps. Plausible; stop all pumps except Charging Pumps and reason is correct. B Correct lAW above discussion.

C Incorrect; also stop the HHSI Pumps. Plausible; want to extend availability ofRWST and HHSI Pumps would still provide core cooling. D Incorrect; don't stop the Charging Pump. Plausible; want to extend availability of R WST and HHSVRHR Pumps would still provide core cooling. Cognitive level: 1 Page 34 of 200 Question #18 ES-401 Question 18 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 --WE12EK2.2 4-EOP-ECA-2.1 step 2 has the crew establish another source offeedwater.

Caution before step 3 has crew maintain a minimum of 25 gpm to any S/G with NR level less than 6%. Step 3.a RNO is to decrease feed to 25 gpm for each S/G is cool down greater than IOO°Flhr.

All ofPTN AFW Pumps are steam driven. Expect to lose steam pressure on all S/Gs and lose the AFW Pumps.

Technical Reference(s):

4-EOP-ECA-2.1 steps 2 & 3 12/19/2005 (Attach if not previously provided)

BO-EOP-ECA-2.1 steps 2 & 3 12/19/2005

(including versionlrevision number) ___________________

_ Proposed references to be provided to applicants during examination:

T.S. 3.3.1 Learning Objective:

6902335 Obi. 3 (As available)

Question Source: Bank # 1.1.26.35.3.3 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x Question #18 ES-401 Question 18 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 1 --WE12EK2.2 4-EOP-ECA-2.1 step 2 has the crew establish another source offeedwater.

Caution before step 3 has crew maintain a minimum of 25 gpm to any S/G with NR level less than 6%. Step 3.a RNO is to decrease feed to 25 gpm for each S/G is cool down greater than IOO°Flhr.

All ofPTN AFW Pumps are steam driven. Expect to lose steam pressure on all S/Gs and lose the AFW Pumps.

Technical Reference(s):

4-EOP-ECA-2.1 steps 2 & 3 12/19/2005 (Attach if not previously provided)

BO-EOP-ECA-2.1 steps 2 & 3 12/19/2005

(including versionlrevision number) __________________

_ Proposed references to be provided to applicants during examination:

T.S. 3.3.1 Learning Objective:

6902335 Obi. 3 (As available)

Question Source: Bank # 1.1.26.35.3.3 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x

. Item: 1.1.26.35.3.3

.9023350303; Unit 4 was at 100% power when the following events occurred:

The main steam header faulted just down stream of the MSIVs.

SI automatically actuated.

The MSIVs did not close and efforts to close them have not been successful.

The RCS has cooled down 150°F in the past 45 minutes and the lowest Tcold is 400°F. Operators are performing ECA-2.1, "Uncontrolled Depressurization of All Steam Generators." Which ONE of the following describes the correct operation of the feedwater system(s)?

A) Establish an alternate feedwater supply equal to 25 gpm per S/G. Isolate the steam supply to all AFW pumps. B) Establish an alternate feedwater supply equal to 345 gpm total flow. Isolate the steam supply to all AFW pumps. C) Establish AFW feedwater flow equal to 25 gpm per S/G. Maintain steam supply to all AFW pumps. 0) Establish AFW feedwater flow equal to 345 gpm total flow. Maintain steam supply to all AFW pumps. CORRECT or INCORRECT feedback for item: 1.1.26.35.3.3

RCO Group 19 Audit Exam 3-EOP-ECA-2.1, Steps 1 & 2 Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

E12 EK3.3 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

A Judging values of alternatives:

A=1 B=-1 C=-1 0=-1 Memo Field:

Reference:

ECA-2.1 step 2 . Item: 1.1.26.35.3.3

.9023350303; Unit 4 was at 100% power when the following events occurred:

The main steam header faulted just down stream of the MSIVs.

SI automatically actuated.

The MSIVs did not close and efforts to close them have not been successful.

The RCS has cooled down 150°F in the past 45 minutes and the lowest Tcold is 400°F. Operators are performing ECA-2.1, "Uncontrolled Depressurization of All Steam Generators." Which ONE of the following describes the correct operation of the feedwater system(s)?

A) Establish an alternate feedwater supply equal to 25 gpm per S/G. Isolate the steam supply to all AFW pumps. B) Establish an alternate feedwater supply equal to 345 gpm total flow. Isolate the steam supply to all AFW pumps. C) Establish AFW feedwater flow equal to 25 gpm per S/G. Maintain steam supply to all AFW pumps. 0) Establish AFW feedwater flow equal to 345 gpm total flow. Maintain steam supply to all AFW pumps. CORRECT or INCORRECT feedback for item: 1.1.26.35.3.3

RCO Group 19 Audit Exam 3-EOP-ECA-2.1, Steps 1 & 2 Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

E12 EK3.3 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

A Judging values of alternatives:

A=1 B=-1 C=-1 0=-1 Memo Field:

Reference:

ECA-2.1 step 2

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 18 Unit 4 was at 100% when the following occurred:

The Main Steam header ruptured downstream ofthe MSIVs.

SI automatically actuated.

The MSIVs did not close and efforts to close them have not been successful.

In accordance with 4-EOP-ECA-2.1, Uncontrolled Depressurization of All Steam Generators, which one of the following describes the correct operation of the feedwater system(s)?

A Establish an alternate feedwater supply equal to 25 gpm per S/G. Isolate the steam supply to all AFW Pumps. B Establish an alternate feedwater supply equal to 130 gpm per S/G. Isolate the steam supply to all AFW Pumps. C Establish AFW feedwater at 25 gpm per S/G. Maintain steam supply to at least one AFW Pump. D Establish AFW feedwater at 130 gpm per S/G. Maintain steam supply to at least one AFW Pump. Page 35 0[200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 18 Unit 4 was at 100% when the following occurred:

The Main Steam header ruptured downstream ofthe MSIVs.

SI automatically actuated.

The MSIVs did not close and efforts to close them have not been successful.

In accordance with 4-EOP-ECA-2.1, Uncontrolled Depressurization of All Steam Generators, which one of the following describes the correct operation of the feedwater system(s)?

A Establish an alternate feedwater supply equal to 25 gpm per S/G. Isolate the steam supply to all AFW Pumps. B Establish an alternate feedwater supply equal to 130 gpm per S/G. Isolate the steam supply to all AFW Pumps. C Establish AFW feedwater at 25 gpm per S/G. Maintain steam supply to at least one AFW Pump. D Establish AFW feedwater at 130 gpm per S/G. Maintain steam supply to at least one AFW Pump. Page 35 0[200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 18 KIA WE 12EK2.2 Steam Line Rupture -Excessive Heat Transfer Knowledge of the relationships between the (Steam Line Rupture -Excessive Heat Transfer) and the following:

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

Reference:

4-EOP-ECA-2.1 steps 2 and 3 Basis Document EOP-ECA-2.1 steps 2 and 3 Step 2 has the crew establish another source of feedwater.

Caution before step 3 has crew maintain a minimum of 25 gpm to any S/O with NR level less than 6%. Step 3.a RNO is to decrease feed to 25 gpm for each S/O is cool down greater than 100°FIhr.

All of PTN AFW Pumps are steam driven. Expect to lose steam pressure on all S/Os and lose the AFW Pumps. History: EXAMINER 1.1.26.35.3.3 Correct answer: A A Correct per above reference and explanation B Incorrect; with a cool down of 150°F, ECA-2.1 step 3.a RNO is to reduce flow to 25 gpm/S/O. Plausible; 345 gpm is PTN normal AFW minimum flow. C Incorrect; ECA-2.1 step 2 is establish an alternate source. Plausible; AFW is normally maintained in the EOP network. D Incorrect; ECA-2.1 step 2 is establish an alternate source. Plausible; AFW is normally maintained in the EOP network. Cognitive level: 2 Candidate has to diagnose conditions and apply correct action Page 36 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 18 KIA WE 12EK2.2 Steam Line Rupture -Excessive Heat Transfer Knowledge of the relationships between the (Steam Line Rupture -Excessive Heat Transfer) and the following:

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

Reference:

4-EOP-ECA-2.1 steps 2 and 3 Basis Document EOP-ECA-2.1 steps 2 and 3 Step 2 has the crew establish another source of feedwater.

Caution before step 3 has crew maintain a minimum of 25 gpm to any S/O with NR level less than 6%. Step 3.a RNO is to decrease feed to 25 gpm for each S/O is cool down greater than 100°FIhr.

All of PTN AFW Pumps are steam driven. Expect to lose steam pressure on all S/Os and lose the AFW Pumps. History: EXAMINER 1.1.26.35.3.3 Correct answer: A A Correct per above reference and explanation B Incorrect; with a cool down of 150°F, ECA-2.1 step 3.a RNO is to reduce flow to 25 gpm/S/O. Plausible; 345 gpm is PTN normal AFW minimum flow. C Incorrect; ECA-2.1 step 2 is establish an alternate source. Plausible; AFW is normally maintained in the EOP network. D Incorrect; ECA-2.1 step 2 is establish an alternate source. Plausible; AFW is normally maintained in the EOP network. Cognitive level: 2 Candidate has to diagnose conditions and apply correct action Page 36 of 200 Question #19 ES-401 Question 19 Written Examination Question Worksheet 6/25/2009 Form ES-401-5 Examination Outline Cross-

Reference:

Level Tier # Group # KiA # RO SRO Proposed Question:

See attached Proposed Answer: Explanation (Optional):

Importance Rating o 1 _2_ 003AK3.09 The RO's error is invisible to rod control, so will attempt to withdraw past ARO. Technical Reference(s):

3-ONOP-028.3 Attachment 1 04/07/2009 (Attach if not previously provided) 5610-T-O-12A 12/17/2007

(including version/revision number) ___________________

_

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902105 Obi. 10 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 This is a substitute KiA. KiA was 003AK3.03 X Question #19 ES-401 Question 19 Written Examination Question Worksheet 6/25/2009 Form ES-401-5 Examination Outline Cross-

Reference:

Level Tier # Group # KiA # RO SRO Proposed Question:

See attached Proposed Answer: Explanation (Optional):

Importance Rating o 1 _2_ 003AK3.09 The RO's error is invisible to rod control, so will attempt to withdraw past ARO. Technical Reference(s):

3-ONOP-028.3 Attachment 1 04/07/2009 (Attach if not previously provided) 5610-T-O-12A 12/17/2007

(including version/revision number) ___________________

_

Proposed references to be provided to applicants during examination:

None Learning Objective:

6902105 Obi. 10 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 This is a substitute KiA. KiA was 003AK3.03 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 19

Rod M -S in Bank D Group 1 dropped into the core earlier.

The crew is recovering rod M-S using 3-0NOP-02S.3, Dropped RCC, Attachment 1, Dropped Rod Recovery.

Bank D Group 1 and 2 Group Step Counters were at 175 steps.

The RO withdraws M-S 165 steps instead of 175 steps.

The crew completes 3-0NOP-02S.3 and commences to return to 100% power. How will the control rods respond to the RO's error? A A pulser failure will cause an urgent failure alarm, preventing all rod motion. B A slave cycler failure will cause an urgent failure alarm, preventing all rod motion. C Bank D Group 1 will continue to withdrawal past all rods out. Bank D Group 2 will stop at all rods out. D Bank D Groups 1 and 2 will continue to demand withdrawal past all rods out. Page 37 0[200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 19

Rod M -S in Bank D Group 1 dropped into the core earlier.

The crew is recovering rod M-S using 3-0NOP-02S.3, Dropped RCC, Attachment 1, Dropped Rod Recovery.

Bank D Group 1 and 2 Group Step Counters were at 175 steps.

The RO withdraws M-S 165 steps instead of 175 steps.

The crew completes 3-0NOP-02S.3 and commences to return to 100% power. How will the control rods respond to the RO's error? A A pulser failure will cause an urgent failure alarm, preventing all rod motion. B A slave cycler failure will cause an urgent failure alarm, preventing all rod motion. C Bank D Group 1 will continue to withdrawal past all rods out. Bank D Group 2 will stop at all rods out. D Bank D Groups 1 and 2 will continue to demand withdrawal past all rods out. Page 37 0[200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 19 KIA 003AK3.09 Dropped Control Rod Knowledge for the reasons for the following responses as they apply to the Dropped Control Rod: Recording of group bank position for dropped rod (reference point used to withdraw dropped rod to equal height with other rods in the bank? NOTE: This is a substitute KIA

Reference:

3-0NOP-028.3 Attachment 1 Both banks are withdrawn to demanded position (in this case 165 steps instead of 175 steps). 561O-T-D-12A The RO's error is invisible to rod control, so will attempt to withdraw past ARO. Question history: New Correct answer: D A Incorrect; error invisible to rod control. Plausible; pulser failure occurs upon failure to generate a pulse when rod motion is demanded.

B Incorrect; error invisible to rod control. Plausible; slave cycler failure occurs when fail to generate pulse when motion is demanded.

C Incorrect; both groups will continue to attempt to move. Plausible; M-8 in group 1 D Correct per above reference.

Cognitive level: 2 Need to analyze for effect ofRO's failure. Page 38 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 19 KIA 003AK3.09 Dropped Control Rod Knowledge for the reasons for the following responses as they apply to the Dropped Control Rod: Recording of group bank position for dropped rod (reference point used to withdraw dropped rod to equal height with other rods in the bank? NOTE: This is a substitute KIA

Reference:

3-0NOP-028.3 Attachment 1 Both banks are withdrawn to demanded position (in this case 165 steps instead of 175 steps). 561O-T-D-12A The RO's error is invisible to rod control, so will attempt to withdraw past ARO. Question history: New Correct answer: D A Incorrect; error invisible to rod control. Plausible; pulser failure occurs upon failure to generate a pulse when rod motion is demanded.

B Incorrect; error invisible to rod control. Plausible; slave cycler failure occurs when fail to generate pulse when motion is demanded.

C Incorrect; both groups will continue to attempt to move. Plausible; M-8 in group 1 D Correct per above reference.

Cognitive level: 2 Need to analyze for effect ofRO's failure. Page 38 of 200

Question #20 ES-401 Question 20 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: 8 Explanation (Optional):

RO 1 _2_ 024AK3.01 Technical Reference(s):

PC8 Section 9 section 6.5 04/10/2009 (Attach if not previously provided) 3-ARP-097.CR 8 8/2 05/05/09 (including version/revision number) 3-0NOP-046.1 steps 2.2 & 2.4 02/29/2008 80 ONOP046.1 steps 2.2 & 2.4 02/29/2008 Proposed references to be provided to applicants during examination:

None Learning Objective:

6902105 Obi. 13 (As available)

Question Source: 8ank# 6/25/2009 Form ES-401-5 SRO Modified 8ank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X *

Question #20 ES-401 Question 20 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: 8 Explanation (Optional):

RO 1 _2_ 024AK3.01 Technical Reference(s):

PC8 Section 9 section 6.5 04/10/2009 (Attach if not previously provided) 3-ARP-097.CR 8 8/2 05/05/09 (including version/revision number) 3-0NOP-046.1 steps 2.2 & 2.4 02/29/2008 80 ONOP046.1 steps 2.2 & 2.4 02/29/2008 Proposed references to be provided to applicants during examination:

None Learning Objective:

6902105 Obi. 13 (As available)

Question Source: 8ank# 6/25/2009 Form ES-401-5 SRO Modified 8ank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 20 In accordance with 3-0NOP-046.1, Emergency Boration, which one of the following events requires emergency boration and why? A A reactor trip occurred 15 minutes ago and Tcolds have decreased to 530 o P. Shutdown margin is not assured. B A reactor trip occurred 15 minutes ago and two rods remained fully withdrawn.

Shutdown margin is not assured. C Bank D rods went below the extra low limit 15 minutes ago. Rod ejection accident analysis assumptions are no longer valid. D Bank D rods went below the extra low limit 15 minutes ago. F lIH could exceed design limits. Page 39 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 20 In accordance with 3-0NOP-046.1, Emergency Boration, which one of the following events requires emergency boration and why? A A reactor trip occurred 15 minutes ago and Tcolds have decreased to 530 o P. Shutdown margin is not assured. B A reactor trip occurred 15 minutes ago and two rods remained fully withdrawn.

Shutdown margin is not assured. C Bank D rods went below the extra low limit 15 minutes ago. Rod ejection accident analysis assumptions are no longer valid. D Bank D rods went below the extra low limit 15 minutes ago. F lIH could exceed design limits. Page 39 of 200

*

06125/2009 Turkey Point ILC 25 NRC Examination Question 20 KIA 024AK3.01 Emergency Boration Knowledge for the reasons for the following responses as they apply to Emergency Boration: When emergency boration is required

Reference:

3-ARP-097.CR B 8/2 PCB Section 9 section 6.5 3-0NOP-046.1 2.2 & 2.4 BD-ONOP-046.l 2.2 & 2.4 History: New Correct answer: B A Incorrect; Tcold less than 525°F requires emergency boration.

Plausible; less than 525°F requires emergency boration.

B Correct; per 0-ONOP-046.1.

C Incorrect; do not have to emergency borate until below insertion limit for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Plausible; reason is correct per PCB. D Incorrect; do not have to emergency borate until below insertion limit for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Plausible; reason is correct per PCB. Cognitive level: 1 Page 40 of 200 *

06125/2009 Turkey Point ILC 25 NRC Examination Question 20 KIA 024AK3.01 Emergency Boration Knowledge for the reasons for the following responses as they apply to Emergency Boration: When emergency boration is required

Reference:

3-ARP-097.CR B 8/2 PCB Section 9 section 6.5 3-0NOP-046.1 2.2 & 2.4 BD-ONOP-046.l 2.2 & 2.4 History: New Correct answer: B A Incorrect; Tcold less than 525°F requires emergency boration.

Plausible; less than 525°F requires emergency boration.

B Correct; per 0-ONOP-046.1.

C Incorrect; do not have to emergency borate until below insertion limit for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Plausible; reason is correct per PCB. D Incorrect; do not have to emergency borate until below insertion limit for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Plausible; reason is correct per PCB. Cognitive level: 1 Page 40 of 200

Question #21 ES-401 Question 21 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 2 02BAG2.2.12 High pressurizer level B/S tripped lAW 4-0NOP-049.l p.42. This is a 2/3 channel trip, so taking another channel OOS will cause a reactor trip. Also, per p. 42, L T -460 is part of the Eagle 21 System. lAW T.S. 3.0.6, can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for testing for the effected channel before returning to service or to demonstrate operability of other equipment.

Technical Reference(s):

..:..T.;...::.

S::..:..-=3;.:..:.0::..:..=3/..=3.:...=.

0:..:...6=1=3=.

________ _ (Attach if not previously provided) 4-0NOP-049.1 OB/11/200B

(including versionlrevision number) ________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902107 Obi. 12.e (As available)

Question Source: Bank# Modified Bank # New __ -:--(Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X

Question #21 ES-401 Question 21 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 1 2 02BAG2.2.12 High pressurizer level B/S tripped lAW 4-0NOP-049.l p.42. This is a 2/3 channel trip, so taking another channel OOS will cause a reactor trip. Also, per p. 42, L T -460 is part of the Eagle 21 System. lAW T.S. 3.0.6, can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for testing for the effected channel before returning to service or to demonstrate operability of other equipment.

Technical Reference(s):

..:..T.:...:.

So..:..-=3c.:..:.

00..:.. 3=1-=.3.:...=.

0:..:.;.6=1=..3.=3..:....1'--

_____ (Attach if not previously provided) 4-0NOP-049.1 OB/11/200B

(including versionlrevision number) ________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902107 Obi. 12.e (As available)

Question Source: Bank# Modified Bank # New __ _:__ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X

*

06/2512009 Turkey Point ILC 25 NRC Examination Question 21 Initial conditions:

Unit 4 is at 100% power.

Pressurizer Level Transmitter L T 460 failed low last month.

All applicable bistables have been tripped in accordance 4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels Subsequently:

4-SMI-041.11, Pressurizer Level Protection Loops Quarterly Test, drop dead date is in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Each Pressurizer Level Channel will be removed from service one at a time. How will the above event affect plant operations?

Note: Tech Spec 3.3.1 is provided as a reference A L T 460 will be bypassed for up to four hours. B 4-SMI-041.11 will be performed without any additional actions. C A plant shutdown will be required to avoid entry into Tech Spec 3.0.3. D A plant shutdown will be required to comply with Tech Spec 3.3.1, Reactor Trip System Instrumentation.

Page 41 0[200 * *

06/2512009 Turkey Point ILC 25 NRC Examination Question 21 Initial conditions:

Unit 4 is at 100% power.

Pressurizer Level Transmitter L T 460 failed low last month.

All applicable bistables have been tripped in accordance 4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels Subsequently:

4-SMI-041.11, Pressurizer Level Protection Loops Quarterly Test, drop dead date is in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Each Pressurizer Level Channel will be removed from service one at a time. How will the above event affect plant operations?

Note: Tech Spec 3.3.1 is provided as a reference A L T 460 will be bypassed for up to four hours. B 4-SMI-041.11 will be performed without any additional actions. C A plant shutdown will be required to avoid entry into Tech Spec 3.0.3. D A plant shutdown will be required to comply with Tech Spec 3.3.1, Reactor Trip System Instrumentation.

Page 41 0[200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 21 KJA 02802.2.12 Pressurizer Level Malfunction Knowledge of surveillance procedures

Reference:

Tech Spec 3.0.3/3.0.6 Tech Spec 3.3.1 4-0NOP-049.1 High pressurizer level B/S tripped lAW 4-0NOP-049.1 p.42. This is a 2/3 channel trip, so taking another channel OOS will cause a reactor trip. Also, per p. 42, LT -460 is part ofthe Eagle 21 System. IA W T.S. 3.3.1 action l3, can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for testing for the effected channel before returning to service or to demonstrate operability of other equipment.

History: New question Correct answer: A A Correct; T.S. 3.0.6 allows bypassing for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to demonstrate operability of other equipment.

B Incorrect; performance of SMI -041.11 without bypassing L T -460 will makeup 2/3 logic and result in reactor trip. Plausible; stem has LT failing low -ONOP-049.1 also trip high level B/S, which is what causes trip. C Incorrect; lAW T.S. 3.0.6 can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Plausible; ifnot aware of3.0.6, would require shutdown.

D Incorrect lAW T.S. 3.0.6 can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Plausible; ifnot aware of 3.0.6, would require shutdown.

Cognitive level: 2 Have to apply T.S. 3.3.1 action 13 to situation Note: provide T.S. 3.3.1 Page 42 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 21 KJA 02802.2.12 Pressurizer Level Malfunction Knowledge of surveillance procedures

Reference:

Tech Spec 3.0.3/3.0.6 Tech Spec 3.3.1 4-0NOP-049.1 High pressurizer level B/S tripped lAW 4-0NOP-049.1 p.42. This is a 2/3 channel trip, so taking another channel OOS will cause a reactor trip. Also, per p. 42, LT -460 is part ofthe Eagle 21 System. IA W T.S. 3.3.1 action l3, can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for testing for the effected channel before returning to service or to demonstrate operability of other equipment.

History: New question Correct answer: A A Correct; T.S. 3.0.6 allows bypassing for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to demonstrate operability of other equipment.

B Incorrect; performance of SMI -041.11 without bypassing L T -460 will makeup 2/3 logic and result in reactor trip. Plausible; stem has LT failing low -ONOP-049.1 also trip high level B/S, which is what causes trip. C Incorrect; lAW T.S. 3.0.6 can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Plausible; ifnot aware of3.0.6, would require shutdown.

D Incorrect lAW T.S. 3.0.6 can bypass channel for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Plausible; ifnot aware of 3.0.6, would require shutdown.

Cognitive level: 2 Have to apply T.S. 3.3.1 action 13 to situation Note: provide T.S. 3.3.1 Page 42 of 200

Question #22 ES-401 Question 22 Written Examination Question Worksheet 6/25/2009 Form ES-401*5 Examination Outline Cross-

Reference:

Level Tier # Group # KIA # RO SRO 1 2 036AK1.03 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference(s):

4-ARP-097.CR B 4/1 03/20/2009 (Attach if not previously provided) 4-0SP-059.1 step 7.3.1.2.a 12/12/2007 (including version/revision number) _________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

.:::.6.=..90;:..:2=-1;....4:.....;4c-O=bic.:... . ...:..10=--

_________ (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 X

Question #22 ES-401 Question 22 Written Examination Question Worksheet 6/25/2009 Form ES-401*5 Examination Outline Cross-

Reference:

Level Tier # Group # KIA # RO SRO 1 2 036AK1.03 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference(s):

4-ARP-097.CR B 4/1 03/20/2009 (Attach if not previously provided) 4-0SP-059.1 step 7.3.1.2.a 12/12/2007 (including version/revision number) _________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: . ...:..1-=..0

__________ (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 22

A core reload is in progress on Unit 4.

N-31 and N-32, Source Range Nuclear Instruments, are at 10 cps before the reload starts. Complete the following:

In accordance with, 4-0SP-059.1, Source Range Nuclear Instrument Analog Channel Operational Test, the Source Range High Flux at Shutdown Alarm is set at (1) . If the alarm actuates the Containment evacuation alarm (2) (1) (2) A 32 cps must be manually actuated B 32 cps will automatically actuate C 50 cps must be manually actuated 0 50 cps will automatically actuate Page 43 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 22

A core reload is in progress on Unit 4.

N-31 and N-32, Source Range Nuclear Instruments, are at 10 cps before the reload starts. Complete the following:

In accordance with, 4-0SP-059.1, Source Range Nuclear Instrument Analog Channel Operational Test, the Source Range High Flux at Shutdown Alarm is set at (1) . If the alarm actuates the Containment evacuation alarm (2) (1) (2) A 32 cps must be manually actuated B 32 cps will automatically actuate C 50 cps must be manually actuated 0 50 cps will automatically actuate Page 43 of 200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 22 KJ A 036AK1.03 Fuel Handling Accident Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Incidents:

Indications of approaching criticality.

Reference:

4-ARP-097.CR B 411 4-0SP-059.1 step 7.3.1.2.a Question history: New Correct answer: B A Incorrect; alarm wiII automatically actuate. Plausible; action ofB 4/1 is to verify alarm actuation

-need to know SR NI circuit. B Correct set at 3.16 x background and will automatically actuate. C Incorrect; set at 3.16 x background and will automatically actuate. Plausible; set Yz decade above background

-need to know that is 3.16 x background

-and need to know SR NI circuit. o Incorrect; set at 3.16 x background.

Plausible; set Yz decade above background

-need to know that is 3.16 x background.

Cognitive level: 3 Need to calculate 10 x 3.16 Page 44 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 22 KJ A 036AK1.03 Fuel Handling Accident Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Incidents:

Indications of approaching criticality.

Reference:

4-ARP-097.CR B 411 4-0SP-059.1 step 7.3.1.2.a Question history: New Correct answer: B A Incorrect; alarm wiII automatically actuate. Plausible; action ofB 4/1 is to verify alarm actuation

-need to know SR NI circuit. B Correct set at 3.16 x background and will automatically actuate. C Incorrect; set at 3.16 x background and will automatically actuate. Plausible; set Yz decade above background -need to know that is 3.16 x background

-and need to know SR NI circuit. o Incorrect; set at 3.16 x background.

Plausible; set Yz decade above background

-need to know that is 3.16 x background.

Cognitive level: 3 Need to calculate 10 x 3.16 Page 44 of 200

Question #23 ES-401 Question 23 Written Examination Question Worksheet 6/25/2009 Form ES-401-5 Examination Outline Cross-

Reference:

Level Tier # Group # KIA # RO SRO 1 2 059AA2.03 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference( s): =..3--=O:..:.N..:..:O::::.:P'---=0:..:6..!..7..::0:..:9,:..:/2:..:.7.:..:/2=0:..:::0c.:...7

_________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

Learning Objective:

6902168 Obi. 7 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 X

Question #23 ES-401 Question 23 Written Examination Question Worksheet 6/25/2009 Form ES-401-5 Examination Outline Cross-

Reference:

Level Tier # Group # KIA # RO SRO 1 2 059AA2.03 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference( s): .=..3--=O:o..;.N..:..O=...:....P--=0:..;:6-'..7-=0:..;:9;..:/2:..:.7.;..:/2=0:..::0:...:..7

_________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

Learning Objective:

6902168 Obi. 7 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 23 The A Monitor Tank (MT) is being released when the following occurred:

Annunciator H 1/4 PRMS HI RADIATION is received in the Control Room.

PRMS-R-I8, Waste Disposal Liquid Effluent Monitor, high alarm is validated.

MT A level is reported to be 75% and slowly lowering.

RCV-OI8, Liquid Waste Discharge Valve, indicates as follows: Red light -on White light -on Green light -on In accordance with 3-0NOP-067, Radioactive Effluent Release, which ofthe following is correct? A RCV-OI8 is open. Close RCV-OI8 from VPB with keyswitch.

B RCV-I8 is open. Close RCV-OI8 from the waste boron panel. C RCV-OI8 is closed. Flush R-I8 and re-initiate the release. D RCV-I8 is closed. IfR-I8 alarm clears, re-initiate the release. Page 450[200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 23 The A Monitor Tank (MT) is being released when the following occurred:

Annunciator H 1/4 PRMS HI RADIATION is received in the Control Room.

PRMS-R-I8, Waste Disposal Liquid Effluent Monitor, high alarm is validated.

MT A level is reported to be 75% and slowly lowering.

RCV-OI8, Liquid Waste Discharge Valve, indicates as follows: Red light -on White light -on Green light -on In accordance with 3-0NOP-067, Radioactive Effluent Release, which ofthe following is correct? A RCV-OI8 is open. Close RCV-OI8 from VPB with keyswitch.

B RCV-I8 is open. Close RCV-OI8 from the waste boron panel. C RCV-OI8 is closed. Flush R-I8 and re-initiate the release. D RCV-I8 is closed. IfR-I8 alarm clears, re-initiate the release. Page 450[200

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 23 KIA 059AA2.03 Accidental Liquid RadWaste Release Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: Failure modes, their symptoms and the causes of misleading indications on a radioactive-liquid monitor

Reference:

3-0NOP-067 Question History: New Correct answer: B A Incorrect; cannot operate RCV-OIS from VPB with keyswitch.

Plausible; can use keyswitch on VPB to override R-I I and R-I2. B Correct; with Monitor Tank level still decreasing and green light lit, RCV-OIS is open and would close from WBP. C Incorrect; valve is open. Plausible; green light is lit, indicating valve is shut and would flush before re-initiating a release D Incorrect; valve is open. Plausible; green light is lit, indicating valve is shut. Cognitive level: 2 Page 46 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 23 KIA 059AA2.03 Accidental Liquid RadWaste Release Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: Failure modes, their symptoms and the causes of misleading indications on a radioactive-liquid monitor

Reference:

3-0NOP-067 Question History: New Correct answer: B A Incorrect; cannot operate RCV-OIS from VPB with keyswitch.

Plausible; can use keyswitch on VPB to override R-I I and R-I2. B Correct; with Monitor Tank level still decreasing and green light lit, RCV-OIS is open and would close from WBP. C Incorrect; valve is open. Plausible; green light is lit, indicating valve is shut and would flush before re-initiating a release D Incorrect; valve is open. Plausible; green light is lit, indicating valve is shut. Cognitive level: 2 Page 46 of 200

Question #24 ES-401 Question 24 Written Examination Question Worksheet 6/25/2009 Form ES-401-5 Examination Outline Cross-

Reference:

Level Tier # Group # KJA# RO SRO 1 2 068AK2.02 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference(s):

0-ONOP-105 Att 3 steps 1 & 2 10/30/2008 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

690252 Obi. 3 & 4 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 7 55.43 x

Question #24 ES-401 Question 24 Written Examination Question Worksheet 6/25/2009 Form ES-401-5 Examination Outline Cross-

Reference:

Level Tier # Group # KJA# RO SRO 1 2 068AK2.02 Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

Technical Reference(s):

0-ONOP-105 Att 3 steps 1 & 2 10/30/2008 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

690252 Obi. 3 & 4 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 7 55.43 x

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 24 In accordance with 0-ONOP-I05, Control Room Evacuation, which of these actions is the Unit 3 RO expected to perform before leaving the Control Room? A Start the A Standby SIG Feedwater Pump Close the MSIVs Verify RCPs running B Trip the reactor Trip the RCPs Close PORV block valves C Trip the Stearn Generator Feedwater Pumps Verify MSIVs open Close PORV block valves D Trip the main turbine Close the MSIVs Start 3B Charging Pump Page 47 of 200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 24 In accordance with 0-ONOP-I05, Control Room Evacuation, which of these actions is the Unit 3 RO expected to perform before leaving the Control Room? A Start the A Standby SIG Feedwater Pump Close the MSIVs Verify RCPs running B Trip the reactor Trip the RCPs Close PORV block valves C Trip the Stearn Generator Feedwater Pumps Verify MSIVs open Close PORV block valves D Trip the main turbine Close the MSIVs Start 3B Charging Pump Page 47 of 200

*

Question 24 KJ A 068AK2.02 Control Room Evac 06125/2009 Turkey Point ILC 25 NRC Examination Knowledge of the interrelations between the Control Room Evacuation and the following:

Reactor Trip System

Reference:

0-ONOP-I05 Attachment 3 steps I & 2 History: New Correct answer: B A Incorrect; RO trips the RCPs. Plausible; RO performs 1 51 two items listed and trips the RCPs B Correct lAW O-ONOP-I 05; RO performs all three actions. C Incorrect; RO closes MSIVs. Plausible; RO performs 1 51 & 3rd items listed and closes MSIVs. D Incorrect; RO stops the 3B Charging Pump. Plausible; RO performs 1 51 two items listed and trips the 38 Charging Pump. Cognitive level: I Page 48 of 200 * *

Question 24 KJ A 068AK2.02 Control Room Evac 06125/2009 Turkey Point ILC 25 NRC Examination Knowledge of the interrelations between the Control Room Evacuation and the following:

Reactor Trip System

Reference:

0-ONOP-I05 Attachment 3 steps I & 2 History: New Correct answer: B A Incorrect; RO trips the RCPs. Plausible; RO performs 1 51 two items listed and trips the RCPs B Correct lAW O-ONOP-I 05; RO performs all three actions. C Incorrect; RO closes MSIVs. Plausible; RO performs 1 51 & 3rd items listed and closes MSIVs. D Incorrect; RO stops the 3B Charging Pump. Plausible; RO performs 1 51 two items listed and trips the 38 Charging Pump. Cognitive level: I Page 48 of 200

Question #25 ES-401 Question 25 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

RO 1 2 074EK1.01 6/25/2009 Form ES-401-5 SRO With 50 gpm HHSI flow, ReS pressure is less than 1600# (approximately 1500#). QSPDS B is not indicating properly.

For Thot given, PT-4-406 has failed to 2235 psig (pre-trip value). All three Thots would not be affected by SI flow. Technical Reference(s): .

__________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

Steam tables Learning Objective: (As available)

Question Source: Bank # Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _8_ 55.43 X *

Question #25 ES-401 Question 25 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

RO 1 2 074EK1.01 6/25/2009 Form ES-401-5 SRO With 50 gpm HHSI flow, ReS pressure is less than 1600# (approximately 1500#). QSPDS B is not indicating properly.

For Thot given, PT-4-406 has failed to 2235 psig (pre-trip value). All three Thots would not be affected by SI flow. Technical Reference(s):

__________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

Steam tables Learning Objective: (As available)

Question Source: Bank # Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _8_ 55.43 X

*

06/25/2009 Turkey Point ILC 25 NRC Examination Question 25 Ini tial Condi ti ons:

Unit 4 was at 100% power.

4A QSPDS has been declared inoperable because of a PT 404 failure. Subsequently:

Unit 4 experienced a LOCA with Safety Injection actuation.

50 gpm of flow is indicated on FI-4-943, Safety Injection Flow.

The crew entered 4-EOP-FR-C.2, Degraded Core Cooling, and started all available Charging Pumps. QSPDS Train B now indicates the following:

Thots are all approximately 525°F.

RCS sub cooling is 126°F. Which of the following correctly describes QSPDS Train B operability and required action(s)?

A QSPDS Train B is indicating properly.

Complete 4-EOP-FR-C.2 then return to procedure and step in effect. B QSPDS Train B is indicating properly.

Stop performance of 4-EOP-FR-C.2 and return to procedure and step in effect. C QSPDS Train B is NOT indicating properly.

Thots are affected by the Safety Injection flow. Manually calculate subcooling.

D QSPDS Train B is NOT indicating properly.

PT-4-406 has failed to pre-trip value. Manually calculate sub cooling. Page 49 of 200 * *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 25 Ini tial Condi ti ons:

Unit 4 was at 100% power.

4A QSPDS has been declared inoperable because of a PT 404 failure. Subsequently:

Unit 4 experienced a LOCA with Safety Injection actuation.

50 gpm of flow is indicated on FI-4-943, Safety Injection Flow.

The crew entered 4-EOP-FR-C.2, Degraded Core Cooling, and started all available Charging Pumps. QSPDS Train B now indicates the following:

Thots are all approximately 525°F.

RCS sub cooling is 126°F. Which of the following correctly describes QSPDS Train B operability and required action(s)?

A QSPDS Train B is indicating properly.

Complete 4-EOP-FR-C.2 then return to procedure and step in effect. B QSPDS Train B is indicating properly.

Stop performance of 4-EOP-FR-C.2 and return to procedure and step in effect. C QSPDS Train B is NOT indicating properly.

Thots are affected by the Safety Injection flow. Manually calculate subcooling.

D QSPDS Train B is NOT indicating properly.

PT-4-406 has failed to pre-trip value. Manually calculate sub cooling. Page 49 of 200

*

Question 25 KIA 074EK1.01 Inad. Core Cooling 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge of the operational implications of the following concepts as they apply to the Inadequate Core Cooling: Methods of calculating sub cooling margin.

Reference:

S team tab I es 4-0P-041.2 With 50 gpm HHSI flow, RCS pressure is less than 1600# (approximately 1500#). QSPDS B is not indicating properly.

For Thot given, PT-4-406 has failed to 2235 psig (pre-trip value). All three Thots would not be affected by SI flow. Question history: New question Correct answer: D A Incorrect; per above discussion, HHSI flow combined with Containment pressure indicates RCS pressure less than 1600 psig. Plausible; if subcooling were correct, core cooling would have been re-established.

B Incorrect; per above discussion, HHSI flow combined with Containment pressure indicates RCS pressure less than 1600 psig. Plausible; if subcooling were correct, core cooling would have been re-established.

C Incorrect; SI flow would affect Tcolds and not all three Thots. Plausible; Tcolds could be affected by SI flow. D Correct per above discussion Cognitive level: 3 Candidate has to use steam tables to determine correct sub cooling margin for conditions gIven. Page 50 of 200 * *

Question 25 KIA 074EK1.01 Inad. Core Cooling 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge of the operational implications of the following concepts as they apply to the Inadequate Core Cooling: Methods of calculating sub cooling margin.

Reference:

S team tab I es 4-0P-041.2 With 50 gpm HHSI flow, RCS pressure is less than 1600# (approximately 1500#). QSPDS B is not indicating properly.

For Thot given, PT-4-406 has failed to 2235 psig (pre-trip value). All three Thots would not be affected by SI flow. Question history: New question Correct answer: D A Incorrect; per above discussion, HHSI flow combined with Containment pressure indicates RCS pressure less than 1600 psig. Plausible; if subcooling were correct, core cooling would have been re-established.

B Incorrect; per above discussion, HHSI flow combined with Containment pressure indicates RCS pressure less than 1600 psig. Plausible; if subcooling were correct, core cooling would have been re-established.

C Incorrect; SI flow would affect Tcolds and not all three Thots. Plausible; Tcolds could be affected by SI flow. D Correct per above discussion Cognitive level: 3 Candidate has to use steam tables to determine correct sub cooling margin for conditions gIven. Page 50 of 200

*

Question #26 ES-401 Question 26 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

3-EOP-ES-I.I step 5 places RHR & HHSI Pumps in standby Technical Reference(s):

3-EOP-ES-1.1 step 5 04/09/2009 (Attach if not previously provided) 5610-T -L 1 sheet 11 04/09/2009 6/25/2009 Form ES-401-5 RO SRO 1 --2 WE02EK2.1 (including version/revision number) __________________

_ Proposed references to be provided to applicants during examination:

Learning Objective:

6902157 Obi. 7 (As available)

Question Source: Bank# 1.1.26.28.2.2 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x * *

Question #26 ES-401 Question 26 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

3-EOP-ES-I.I step 5 places RHR & HHSI Pumps in standby Technical Reference(s):

3-EOP-ES-1.1 step 5 04/09/2009 (Attach if not previously provided) 5610-T -L 1 sheet 11 04/09/2009 6/25/2009 Form ES-401-5 RO SRO 1 --2 WE02EK2.1 (including version/revision number) __________________

_ Proposed references to be provided to applicants during examination:

Learning Objective:

6902157 Obi. 7 (As available)

Question Source: Bank# 1.1.26.28.2.2 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x 1-... . ..

Item: 1.1.26.28.2.2

.9023280202; Unit 3 has experienced a steam line break on the common steam header and a SI actuation.

The steam line break has been isolated and the crew terminated the SI in accordance with EOP-ES-1.1, SI Termination.

All SI signals have cleared.

The unit subsequently experiences a steam generator tube rupture and RCS pressure drops to 1200 psig. What is the status of the HHSI pumps? The HHSI pumps are: A) running. They were left running after ES-1.1 was competed.

8) running. They started when pressurizer pressure dropped below 1730 psig. C) NOT running. They were placed in pull-to-Iock in ES-1.1. 0) NOT running. SI reset blocked their auto start from any subsequent SI signal. CORRECT or INCORRECT feedback for item: 1.1.26.28.2.2 RCO Group 19 Audit Exam EOP-ES-1.1 step 5; 5610-T-L 1 Sh 11 Item Classification:

Comprehension

em difficulty:

0.50 ,eywords:

006 K4.11 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

8 Judging values of alternatives:

A=-1 8=1 C=-1 0=-1 1-... . ..

Item: 1.1.26.28.2.2

.9023280202; Unit 3 has experienced a steam line break on the common steam header and a SI actuation.

The steam line break has been isolated and the crew terminated the SI in accordance with EOP-ES-1.1, SI Termination.

All SI signals have cleared.

The unit subsequently experiences a steam generator tube rupture and RCS pressure drops to 1200 psig. What is the status of the HHSI pumps? The HHSI pumps are: A) running. They were left running after ES-1.1 was competed.

8) running. They started when pressurizer pressure dropped below 1730 psig. C) NOT running. They were placed in pull-to-Iock in ES-1.1. 0) NOT running. SI reset blocked their auto start from any subsequent SI signal. CORRECT or INCORRECT feedback for item: 1.1.26.28.2.2 RCO Group 19 Audit Exam EOP-ES-1.1 step 5; 5610-T-L 1 Sh 11 Item Classification:

Comprehension

em difficulty:

0.50 ,eywords:

006 K4.11 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

8 Judging values of alternatives:

A=-1 8=1 C=-1 0=-1 06/25/2009 Turkey Point ILC 25 NRC Examination Question 26

Unit 3 has experienced a steam line break on the common steam header.

Safety injection (SI) actuated.

The steam line break has been isolated.

The crew terminated SI in accordance with 3-EOP-ES-1.1, SI Termination.

All SI signals have cleared. The unit subsequently experiences a steam generator tube rupture and RCS pressure drops to 1200 psig. What is the status of the HHSI Pumps? The HHSI Pumps are ... A runnmg. They auto started when Pressurizer pressure dropped below 1730 psig. B runnmg. They auto started due to the 100 psid Steam Line signal. C NOT running. The sequencer must be reset before it can see another SI signal. D NOT running. SI reset blocked their auto start from any subsequent SI signal. Page 51 o f 200

06/25/2009 Turkey P o int IL C 25 NRC Examination Question 26

Un it 3 has experienced a stea m line break o n t h e co mm on s t eam header.

Safe t y injection (Sf) actuated.

The s te am line break has been i s o l ated.

The c r ew tenninated S I in accordance with 3-EOP-ES-1. I. S I Tennination.

A ll SI signa l s h ave cleared. The unit subseque n tly experie n ces a steam ge n era tor tube rupture and Res pressure drops to 1 200 psig. What is t h e sta t us of th e HHSI Pumps? Thc HHS I Pumps arc ... A funnmg. The y auto s t arted when Pressurizer pressure dropped be l ow 1 730 psig. B runmng. They a ut o started due to the 1 00 psid Steam Line signal. C NOT running. The seque n cer must be r eset before it can sec another S I signal. o NOT runnin g. S I r eset b l ocked their au t o start from any subsequent S I signa l. Pa ge 51 of 200 0612512009 Turkey Point ILC 25 NRC Examination Question 26 KIA WE02EK2.1 SI Tennination Knowledge of the interrelations between the (SI Termination) and the following:

Components and functions of controls and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features

Reference:

3-EOP-ES-1.1 step 5 places RHR & HHSI Pumps in standby 5610-T-Ll sheet 11 Question history: EXAMINER 1.1.26.28.2.2 Correct answer: A A Correct; with all SI signals cleared after reset, 2/3 Pressurizer pressure less than 1730 will re-initiate S I. B Incorrect; steam line break was on common steam header, so SGTR will not increase Containment pressure.

Plausible; SGTR with previous steam line break inside Containment could increase Containment pressure.

C Incorrect; Pumps placed in standy in ES-l.1. Plausible; Pumps are stopped in ES-l.l. o Incorrect; when all SI signals cleared, block is removed. Plausible; need to realize block removed when SI clears. Cognitive level: 2 Candidate needs to put together that SI signal no longer blocked when all signals clear. Also needs to realize that Containment pressure will not increase with this steam line break location.

Page 52 of 200 *

06/2512009 Turkey Point IL C 25 NRC Exam in at ion Question 26 KJA WE02EK2.1 S I Tennination Knowledge of the int errelatio n s between th e (S I Termination) a nd the following:

Co mp onents and functions of contro l s and safety systems, including instrumentation, s ign a l s , interlocks , fai lur e modes a nd automatic and manual features

Reference:

3-EOP-ES-I.1 step 5 places RHR & HHSI Pumps in standby 561O-T-LI sheet II Question hi story: EXAMINER 1.1.26.28.2.2 Correct answer: A A Correct; wi th all S I s i gnals cleared after 2/3 Pressurizer pressure le ss than 1 730 w ill re-initiate S I. B In co rr ect; steam lin e break was on commo n steam header , so SGTR w ill not increase Conta inm ent pressure.

Plausible; SG TR wi th previous steam line break inside Conta inm en t cou ld increase Containme nt pressure . C In correct; Pumps placed in s t a nd y in ES*I. t. Plau sib l e; Pumps are stopped in ES*I.l. D In correc t; when all SI signa l s cleared, block is r emoved. Plausible; ne ed to rea li ze block removed w h e n S I clears. Cogn iti ve level: 2 Can didat e needs t o put together that S I signa l no longer b l ocked whe n a Jl sig nal s clear. Also needs t o rea li ze that Contai nment pressure wi ll not increase with this s team lin e break l ocat i o n . Pag e 52 of 20 0 Question #27 ES-401 Question 27 Written Examination Question Worksheet 6/25/2009 Form ES-401-5 Examination Outline Cross-

Reference:

Level Tier # Group # KIA # RO SRO 1 2 WE16EA1.1 Importance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

Technical Reference(s):

3-EOP-ECA-Z

.3 step 1.b 04/15/1999 (Attach if not previously provided) 5613-M-3053 03/14/2005 (including versionlrevision number) ___________________

_ Proposed references to be provided to applicants during examination

Learning Objective:

6902129 Obi. 5 (As available)

Question Source: Bank # 1.1.26.38.3.3 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x

Que s tion #2 7 ES-401 Question 27 Written Examination Question Workshe et Examination Outline Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answe r: D Explanation (Optional)

Technical Reference(s)

3-EOP-ECA-Z.3 step 1.b 04/15/1999 (Attach if not previously provided) 5613-M-3053 03/14/2005 6/25 12 009 Form RO SRO 1 --2 W E16EA1.1 .2l .2L (including version/revision number) __________________

_ Proposed references to be provided to applicants during examination

Learning Objective: 6902129 Obi. 5 (As available)

Question Source: Bank # 1.1.26.38.3.3 Modified Bank # __ ,,-(Note changes or attach parent) New Question Hi story: Last NRC E xam (Optional: Questions valida/ed at the facitity since 10/95 wilt generalty undergo tess rigorous re v iew by the NRC; failure to provide the in formation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.26.38.3.3 9023380303

he following conditions exist on Unit 3 with the unit initially in Mode 3: -A Containment purge was in progress. -A LOCA occurred and operators responded using the EOP network. -Operators are performing FR-Z.3. "Response to High Containment Radiation Level." -POV-2602 , Containment Purge Exhaust Isolation Valve, will NOT close from VPB. Which ONE of the following describes the required operator response?

A) Dispatch an operator to locally close POV-2602. B) Verify its series isolation valve , POV-2603 , is closed. C) Fail POV-2602 closed by pulling its fuse behind VPB. D) Dispatch an operator to close POV-2602 at the Alternate Shutdown Panel. CORRECT or INCORRECT feedback for item: 1.1.26.38.3.3 RCO Group 19 Audit Exam EOP-FR-Z.3 , Step 1.b.RNO Item Classification

Knowledge m difficulty:

0.50 eywords: LOP, E16 EK2.1 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

C Judging values of alternatives

A=-1 8=-1 C=1 D=-1 Memo Field:

Reference:

FR-Z.3 Step 1 b RNO Items in G:\Trng"-'\pps\WEXAM!NE\PTN Exam\P TN Exam.xam Item: 1.1.26.38.3.3 9023380303:

he following conditions exist on Unit 3 with the unit initially in Mode 3: -A Containment purge was in progress. -A LOCA occurred and operators responded using the EOP network.. -Operators are performing FR-Z.3. "Response t o High Containment Radiation Level." -POV-2602 , Containment Purge Exhaust Isolation Valve, will NOT close from VPB. Which ONE of the following describes the required operator response?

A) Dispatch an operator to l ocally close POV-2602. B) Ver i fy its series isolation valve , POV-2603 , is closed. C) Fail POV-2602 dosed by pulling its fuse beh i nd VPB. D) Dispatch an operator to close POV-2602 at the Alternate Shutdown Panel. CORRECT or IN CORREC T feedback for item: 1.1.26.38.3.3 RCO Group 19 Audit Exam EOP-FR-Z.3, Step 1.b.RNO Classification

Knowledge m difficulty

0.50 eywords: lOP , E16 EK2.1 Item weight 10 Points required for mastery: 1 Co rrect alternative(s)

C Judging values of alternatives

A=-1 B"'-1 C"'1 D=-1 Mem o Field:

Reference:

FR-Z.3 S t ep 1b RNO 06/25/2009 Turkey Point ILC 25 NRC Examination Question 27

A Containment purge was in progress on Unit 3.

A LOCA occurred.

The crew is responding to high containment radiation level.

POV 2603, Containment Purge Exhaust Isolation Valve, will not close manually.

In accordance with 3-EOP-FR-Z.3, Response to High Containment Radiation Level, how will POV-3-2603 be closed? A Dispatch an operator to close POV-3-2603 from the Alternate Shutdown Panel. B Dispatch an operator to locally close POV-3-2603.

C Fail POV-3-2603 closed by pulling its fuse behind VP A. D Fail POV-3-2603 closed by pulling its fuse behind VPB. Page 53 of 200

06/25/2009 Turkey P oint IL C 25 N R C Examination Question 27

A Con tainm ent pur ge was in progress o n Uni t 3.

A LOCA occu rr ed.

The crew is responding to hi g h co nt ainment r adiat i o n level.

POV-3-2603 , Conta inm ent Purge Ex h aust I solation Va l ve , will not close manua ll y. In accordance with 3-EO P-FR-Z.3, Response to Hi gh Co nt a inment Radiation Level , h ow wi ll POV-3-2603 be closed? A Dispatch an operator 1 0 close POV 2603 from the A lternat e Shutdown Panel. B Dispatch an opera t or to l ocally close POV-3-2603.

C Fail POV-3-2603 closed by pu llin g i ts fuse behind V P A. D Fail POV-3-2603 closed by pu llin g i ts fuse behind VPB. Pag e 53 of20 0 06/2512009 Turkey Point ILC 25 NRC Examination Question 27 KJA WE16EA1.1 High Containment Radiation Ability to operate and 1 or monitor the following as they apply the (High Containment Radiation):

Components and functions of control and safety systems, including instrumentation signals, interlocks, failure modes and automatic and manual features.

Reference:

3-EOP-FR-Z.3 step 1.b 5613-M-3053 History: EXAMINER 1.1.26.38.3.3 modified Correct answer: D A Incorrect; not on alternate shutdown panel. Plausible; sometimes in EOP network components are checked on ASP. B Incorrect; POV-3-2603 is inside Containment.

C Incorrect; behind VPB. Plausible; need to know where operated from. o Correct; lAW 3-EOP-ECA-Z.3 Cognitive level: 1 Page 54 of 200 0 6/25/2 0 0 9 Tu r k ey P o int IL C 25 N R C E xa minati o n Q u es t io n 27 KIA WE I 6EA I.I High Co ntainm e nt R a di a t io n A bilit y to o p era te a nd I or m o nit o r th e fo ll ow in g as t hey a ppl y the (High Co ntainm e nt Rad i a t i o n): Co mp o n e nt s and fun c ti o ns o f co ntr o l and s af e t y sys t e m s, includin g in s trum e nt a ti o n s i gna l s , int e rl oc k s, f a i l ur e m o d es a nd a ut o m a t ic a nd manu al f ea tur es. R e f e r e n ce: 3-EO P-F R-Z.3 st e p I.b 5 61 3-M-3053 H is t ory: E XA MI NER 1.1.26.38.3.3 m o difi e d Correct answer: D A In co rr ect; n o t o n a lt e rn a te s hut down p ane l. P l a u s ib l e; so m e tim es i n EOP n e t wo rk co mp o n e nt s are c h ec k e d o n AS P. B I n co rr ec t; P OV-3-2603 i s in s id e Co ntainment. C In co rr ec t; b e h i nd V PB. Plau s i b l e; n ee d to kn ow w h e re o p e rat e d from. D Corr e c t; l AW 3-EO P-ECA-Z.3 Cog niti ve l eve l: I Page 54 o f 200 Question #28 ES-401 Question 28 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional)

RO 2 1 003A3.02 6/25/2009 Form ES-401-5 SRO IA W BD OP-041.1, motor current will go off-scale to near 5000 amps for cold start and return to normal in 22 seconds. Also, can use flow to indicate pump coming up to speed. Technical Reference(s):

_________

_ (Attach if not previously provided)

BO-OP-041.1 03/05/2008 (including versionlrevision number). ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902108 Obi. 6 & 10 (As available)

Question Source: Bank # Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X

Qu es ti o n #2 8 6 12 512 009 ES-401 Written Examination Form ES-401-5 Question Worksheet Question 28 Examination Outline Cross-Reference

Level RO SRO Tier # 2 Group # 1 --KIA # 003A3.02 Importance Rating ..ll.. ...ll. Proposed Question:

See attached Proposed Answer: B Explanation (Optiona l): I A W BD OP-04 1.1. mOl o r c urr e nt w ill g o ofT-s cale to n e ar 5 0 0 0 a mp s ror co ld s tart a nd return to n o ml a l in 22 seco nd s. A l so. c an u se flow t o indicate pump co min g up to s peed. Technical Reference (s):

________ _ (Attach if not previously provided)

BD-OP-041.1 03/05/2008 (inc lud ing version/revision number) ________________

____ _ Proposed references to be provided to applicants during e x amination: None Learn ing Object i ve: 6902 1 08 Obj. 6 & 10 (As available)

Quest i on Source: Bank # Modified Bank # New __ .,,-(N ote changes or attach paren t) X Question History: Last NRC Exam (Optiona l: Questions val id a t ed a t th e fa cili t y since 10195 w i ll generally undergo J e s s rigoro u s rev iew b y t he NR C; f ailu re 1 0 provide t he in f O/m a t ion will necessi t a t e a d eta ile d re vie w o f eve ry q ues t ion.) Question Cogniti v e Level: 10 CFR Part 55 Content: Comment s: Memory or Fundamental Knowledge Comprehension or Anal y sis 55.41 55.43 7 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 28

Unit 4 is in Mode 5.

The 4A RCP is being started. In accordance with 4-NOP-041.0IA, 4A Reactor Coolant Pump Operations, how will the 4A RCP current and flow respond? RCP current will

__ then return to normal. Flow indication will start to Increase (2) (1) (2) A peg off-scale high after current is back to normal B peg off-scale high while current is off-scale C remain on scale after current is back to normal D remain on scale while current is at the top of the meter Page 55 of 2 0 0 *

06/25/2009 Turkey P o int IL C 25 N R C E x aminati o n Question 28

U nit 4 i s in M o d e 5.

The 4A R e p i s bein g started. In acco rdan ce with 4*NOp*041.0 I A , 4A R eac t or Coolant Pump Operat i ons , h ow wi ll th e 4A R e p c urr ent and fl ow r espo nd? R e p c urr e n t will_--.J("I.L)

__ then return to n onna l. Fl ow indi ca tion will s t a rt to Incr ease (2) ( I) (2) A peg off-sca l e hi gh after cu rrent i s ba c k to nonnal B peg off-sca l e hi g h while c urr e nt is o ff-sca le C rem a in on sca le after current i s back 1 0 nonnal D r e m a in o n sca l e whi le c urrent is at the top of th e meter Pag e 55 o f 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 28 KJA 003A3.02 Reactor Coolant Pump Ability to monitor automatic operation of the RCPS, including:

Motor current

Reference:

4-NOP-041.01A Basis Document OP-041.1 IA W BD OP-041.1, motor current will go off-scale to near 5000 amps for cold start and return to nonnal in 25 seconds. Also, can use flow to indicate pump coming up to speed. History: New question Correct answer: B A Incorrect; flow will start to increase before amps come back on scale. Plausible; need to know that flow will start to increase shortly after start and while current still pegged high. B Correct; lAW Basis Document C Incorrect; meter only goes to 1200 amps. Plausible; current could only go to top of meter. D Incorrect; meter only goes to 1200 amps. Plausible; current could only go to top of meter. Cognitive level: 1 Page 56 of 200 *

06/25/2009 Turkey Point IL C 25 N R C Examination Question 28 KIA 003A3.02 Reactor Coo l an t Pump Ab ilit y to monitor au t omatic ope r at i o n of the RepS, including:

Motor curre nt R eference:

4-NOP-04 1.01 A Basis Document OP*041.1 l AW SO OP-04J.l, motor curre nt wi ll go off-sca l e to n ear 5000 a mp s fo r co ld sta rt a nd r etu m to n orma l in 25 seconds. A l so, can use flow to indicate pump coming up to speed. History: New question Co rr ec t answe r: B A I ncorrect; flow will start to in crease before amps come back on sca l e. Plausible; need to know that flow wi ll start to increase short ly after start a nd while c urr en t st ill pegged high. B Correc t; l AW Basis Document C I ncorrect; meter on l y goes to 1200 amps. Plausible; current could only go to top of meter. o In correct; meter only goes to 12 00 amps. Plausible; curre nt cou ld only go to top of meier. Cog niti ve level: 1 Page 56 o f200 Question #29 ES-401 Question 29 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional):

Technical Reference(s):

3-ARP-097.CR G 2/1 05/08/2009 RO 2 1 003A4.05 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided) 3-0NOP-04.1 NOTE before step 37 11/27/2007 (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902108 Obi. 7 (As available)

Question Source: Bank# Modified Bank # New 1.1.24.8.6.2 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional: Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x *

Question #29 ES-401 Question 29 Written Examination Question Worksheet E xam inat io n Outline C ross-Reference

L evel Tier # Group # KIA # Im portance Rating Prop osed Question: See attached Proposed Answer: D E x planatio n (Op ti on al): Te chnical Reference(s)

3-ARP*097.CR G 2/1 05/08/2009 RO 2 1 003A4.05 6/2 5/2 009 Form ES-401-5 SRO (Attach if not previously prov i ded) 3-0 NOP*0 4.1 NOTE before step 37 1 1/27/2007 (i nclud i n g version/revision n umber) _________________

__ _ Proposed r e feren ces to be provided to applicants during e xa minat ion: N o ne Learning Objective: 6902 108 Obi-7 (As available)

Question Source: Bank # Modified Bank # Ne w 1.1.24.8.6.2 (Note c hang es or attach parent) Question Histo ry: Last NRC Exam (Optional: Questions validated at the facUity since 10/9 5 will generally undergo less rigorous review by the NRC; failure /0 provide the in formati on wilt ne cessit ate a detailed review of every question.)

Question Cogni t ive L evel: 1 0 CFR Part 55 Con tent: Comments: Memory or Fundamental Knowledge Comprehens i on or Analysis 55.4 1 55.43 7 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.B.6.2 9021080602; Given:

Annunciator G-2/1 , RCP A STANDPIPE HI LEVEL, has alarmed.

3A RCP #1 sealleakoff flow has decreased from 2 gpm to 1 gpm. The above is indicative of: A) Decreased seal injection flow 8) Increased seal injection flow C) #1 seal failure D) #2 seal failure CORRECT or INCORRECT feedback for item: 1.1.24.B.6.2 RCO Group 19 Audit Exam 3-ARP-097.CP ARP G-2/1; ONOP-41.1 NOTES before step 37 Item Classification:

Comprehension Item difficulty:

0.50 Keywords:

LOP, 003 A4.06 Item weight: 10 Points required for mastery: 1 orrect alternative(s)

D udging values of alternatives:

A=-1 8=-1 C=-1 D=1 Memo Field:

REFERENCE:

SD-OOB OPS APPROVED T.S. 3/29/04 Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.8.6.2 9021080602

Given

Annunciator G-2/1, RCPA STANDP I PE H I l EVEL , has alarmed.

3A Rep #1 sealleakoff flow has decreased from 2 gpm to 1 gpm. T h e above is indicative of: A) Decreased seal i njection flow B) I ncreased seal injection flow C) #1 seal failure 0) #2 seal failure CORRECT or INCORRECT feedback for item: 1.1.24.8.6.2 RCO Group 19 Audit Exam 3-ARP-097.CP ARP G-2/1; ONOP-41.1 NOTES before step 37 Item Classification

Comprehension Item difficulty

0.50 Keywords: LOP , 003 A4.06 Item weight: 10 Points required for mastery: orfect alternative(s

): 0 dging values o f alternatives

A=-1 8=-1 C=-1 0=1 Memo Field:

REFERENCE:

SO-008 OPS APPR OVED T.S. 3129/0 4 06/25/2009 Turkey Point ILC 25 NRC Examination Question 29

Annunciator G 211 , RCP A STANDPIPE HI LEVEL, has alanned.

3A RCP #1 sealleakoffflow has decreased from 2 gpm to 1 gpm. In accordance with 3-0NOP-041.1 , Reactor Coolant Pump Off-Nonnal, which of the following is the most probable cause of the above conditions?

A RV-3-382 , Seal Return Relief Valve, failed open B CV-3-303A, 3A RCP Seal LeakoffIsolation Valve failed closed C Number I seal failure o Number 2 seal failure Page 57 o f 200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 29

Annunciator G 211, RCP A STANDPIPE HI LEVEL , ha s alarmed.

3A Rep # 1 seal leakoff flow has decreased from 2 gpm to 1 gpm. In accordance with 3*0NOP-041.

1 , Reactor Coolant Pump Off-Nonna!, which of the following is the most probab l e cause of the above conditions?

A RV-3-382, Seal Return Re l ief Valve, failed open B CV-3-303A, 3A RCP Sea l Leakoffl so lation Valve failed closed C Number I seal failure D Number 2 sea l failure Page 57 of200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 29 KIA 003A4.05 Reactor Coolant Pump Ability to manually operate andlor monitor in the control room: RCP seal leakage detection instrumentation

Reference:

3-ARP-097.CR G 211 -cause of alarm is #2 seal damage 3-0NOP-041.1 NOTE before step 37 Question history: EXAMINER 1.1.24.8.6.2 Correct answer: 0 A Incorrect; standpipe would not increase.

Plausible; would decrease indicated seal return flow. B Incorrect; seal leakoff would be zero. Plausible; would increase standpipe level. C Incorrect;

1 seal failure would have less flow through #2 seal. Plausible; need to understand how RCP seals work. o Correct per above references Cognitive level: 2 Page 58 0[200 06/25/2009 Turkey Point IL C 25 NRC Examination Q u estion 29 KIA 003A4.05 Reactor Coo l an t Pump Abi li ty to manu a ll y operate and/or monitor in the con t rol room: Rep sea l leakage detection instrumentation

Reference:

3-ARP-097.CR G 211 -cause ofalann is #2 sea l damage 3-0NOP-04 1.1 NOTE before s t ep 37 Question history: EXAM I NER 1.1.24.8.6.2 Correct answer: 0 A In correct; standpipe would not increase.

Pl ausible; would decrease indicated sea l return flow. B In corrcct; seal l eakoffwou ld be zero. Plausible; wou ld increase standpipe level. C Incorrect;

1 sea l fai lur e wou ld have less flow through #2 seal. Plausible; need to understand how Rep seals wo rk , o Correct per above references Cognitive level: 2 Pa ge 5 8 or 200 Question #30 ES-401 Question 30 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

Technical Reference(s):

3-0NOP-041.111/27/2007 RO 2 1 004K6.31 (Attach if not previously provided)

________________

_ 6/25/2009 Form ES-401-5 SRO (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902110 Obi. 5 (As available)

Question Source: Bank # 1.1.25.5.3.1 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x

Question #30 6/25 1 2009 ES-401 Written E xamination Form ES-401-5 Question Worksheet Question 30 Examination Outline Cross-Reference

Le vel RO SRO Tier # 2 Group # 1 --KIA # 004K6.31 Importance Rating -lL Proposed Question

See attached Proposed Answer: C Explanation (Optional)

Technical Reference(s)

3-0NOP-041

.1 11127/2007 (Attach if not previously provided),:;-

_______________

_ (including ve r sion/revision number) ____________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902110 Obi. 5 (As available)

Question Source: Bank # Modified Bank # Ne w 1.1.25.5.3.1 ==;.,-(Note changes or attach parent) Question Hist ory: Last NRC Exam (Oplional.

-Questions validated al the facility since 1Q195 will generally undergo less rigorous review by the NRC; failure to provrde the in format ion will necessit ate 8 de/ailed review of every question)

Question Cognitive Level: 10 C FR Part 55 Conlen!: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.25.5.3.1 9 022050301

The following conditions exist

The reactor is at power.

POWER ABOVE P-8 status light is dark (extinguished).

One charging pump is running with a discharge pressure higher than RCS pressure.

Annunciator A-6/6, SEAL WATER INJ FILTER HI DP , alarms.

Local seal water injection flows (FI-124 , 127 , and 130) indicate 2, 3, and 2 gpm respectively.

The standby seal water injection filter is NOT available. Which ONE of the following describes the actions required under these circumstances?

A) Commence a normal plant shutdown and stop all RCPs within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 8) Maintain component cooling water flow to the thermal barrier. C) Trip the reactor and stop all RCPs. 0) Bypass the seal injection filters. Item Classification

Knowledge m difficulty

0.50 eywords: 003 A2.02, RCO Item weight: 10 Points required for mastery: 1 Correct alternative(s)

8 Judging values of alternatives:

A=-1 8=1 C=-1 0=-1 Memo Field:

REFERENCES:

3/4-0NOP-041

.1 steps 1415, H8R RCO 7/94 Q 04 Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.25.5.3_1 022050301:

The following conditions exis t

The reactor is at power.

POWER ABOVE P-8 status light is dark (extinguished).

One charging pump is running with a discharge pressure higher than RCS pressur e.

Annunciator A-6/6, SEAL WATER I NJ FILTER HI DP , alarms.

Lo c al seat water injection flows (FI-124 , 127, and 130) indicate 2 , 3, and 2 gpm respe c tively.

The standby seal water injection filter is NOT available. Which ONE of the follow in g desc r ibes the actions required under these circumstances?

A) Co mmence a normal plant shutdown and stop all RCPs within 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . B) Maintain compo nent cooling water flow to the thermal barrier. C) Trip the reactor and stop all R C Ps. 0) Bypass the seal i n jection filters. It em C las sifica t io n: Knowledge m difficulty

0.50 eywords: 003 A2.02, RCO lIem weight: 10 Points req ui red f or mastery: 1 Co rr ect alternative(s

): 8 Judging values o f alt e rnatives: A=-1 8=1 C=-l 0=*1 M e m o Field: REFERENCES

3/4-0NOP*041_1 steps 14 15 , HBR RCO 7194 Q 0 4

0612512009 Turkey Point ILC 25 NRC Examination Question 30

Unit 3 is at 100% power.

Annunciator A 6/6, SEAL WATER IN] FILTER HI DP, actuates.

The standby filter is not available

Local seal injection flows indicate about 2 gpm to each RCP. In accordance with 3-0NOP-041.1, Reactor Coolant Pump Off-Normal, which one of the following describes required action(s)?

A Trip the reactor and stop all RCPs B Bypass the RCP seal injection filters C Maintain CCW flow to the RCP thermal barriers D Shutdown the unit and stop all RCPs within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Page 59 of 200 06/2 5/20 0 9 Turk ey P o int IL C 25 N RC E xamin a t io n Q u es ti o n 3 0

Unit 3 is a t 10 0% p ow er.

Annun c i a t o r A 6/6, SEAL W A T E R fN J FILT E R HI DP , a c tu a t es.

Th e s t a ndb y fil ter i s n ot a va i l a ble

L oca l s eal inj ec ti o n flo ws i ndi ca te ab o ut 2 gpm t o eac h R e p. In acco rd a n ce w ith R e act o r Coo l a nt Pump Off-No rm a l , whi c h o nc of th e f o ll ow in g d esc ribe s re qui r e d ac tion (s)? A Trip the r eac t o r a nd s top a ll R e p s B B ypass th e R e p sea l inj ec ti o n filt e r s C M a int a in CC W fl ow t o th e R e p th e rm a l b a rn e r s D S hutd o wn th e un it a nd s t o p a ll R e p s w ithin 1 2 h o ur s P lIgc 59 of 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 30 KJA 004K6.31 Chemical Volume Control Knowledge of the effect of a loss or malfunction on the following will have on Chemical Volume Control: Seal injection system and limits on flow range

Reference:

3-0NOP-041.1 Question history: EXAMrNER 1.1.25.5.3.1 Correct answer: C A Incorrect; do not need to trip the unit. Plausible; numerous seal failures require reactor trip. B Incorrect; ONOP-041.1 isolates seal injection filters if not available. Plausible; this would increase seal injection flow. C Correct lAW 3-0NOP-041.1.

D Incorrect; plant shutdown required, but not within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Plausible; 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months to commence shutdown and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to stop RCPs. Cognitive level: 2 Need to determine actions for seal injection malfunction Page 60 of 2 00 *

06/25/2009 Turkey P o int IL C 25 NRC Examination Question 30 KIA 004K6.31 Chem i ca l Vo lum e Co ntr o l Kn ow led ge of the effect of a l oss or malfunction o n the following wi ll ha ve o n Chemica l Volume Contro l: Sea l inj ec tion system and limit s on flow range

Reference:

3-0NOP-041.1 Que s ti on hi s tory: EXAMINER 1.1.25.5.3.1 Correct answer: C A In co rre c t; d o not need to trip the unit. Plau s ibl e; numerous sea l failure s require reactor trip. B In co rre ct; ONOP-041.1 i s olates s eal injection filters jf not avai lable. Plausible; thi s would incr ease sea l injection fl ow. C Correel l AW 3-0NOP-041.1.

D In co rre c t; p l ant s hutdown required, but not within 1 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s. Plau s ible; 1 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to co mmence s hutd ow n a nd 24 h o ur s to s t op Reps. Cognitive level: 2 Ne ed to dctcnnine act i ons for s eal injection malfunction Page 60 of 200 Question #31 ES-401 Question 31 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: B Explanation (Optional)

RO 2 1 005A4.05 6/25/2009 Form ES-401-5 SRO Per the cautions , cavitation may occur. This flowpath robs flow from 605, decreasing flow to core and indicated flow will also decrease. Technical Reference(s):

5613-M-3050 sheet 1 03/25/2009 (Attach if not previously provided) 3-0P-201 cautions & note before step 6.1.2.9 & step (including version/revision number)_6.:::.;.:....:.1..:..:. 2::.:... 9:::.....::::0.=.3/'-'1'-'=3"-'/2::.=0:..:::0:.:::9

__________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902121A Obi. 9c (As available)

Question Source: Bank # Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.) Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X

Question #3 1 612512009 ES-401 Written Examination Form ES-401-5 Question Worksheet Question 31 Examination Outtine Cross-Reference

Level RO SRO Tier # 2 --Group # 1 --KIA # 005A4.05 Importan ce Rating Proposed Question: ' See attached Prop osed Answer: B Explanation (Optional): Per the ca uti o n s, cav itati on may occ ur. This Il ow path robs flo w from 605 , d ec rea s in g fl ow t o core and indi cated flow w ill al so decrea se. Technica l Reference(s

): 5613-M-3050 sheet 103125/2009 (Attach if not previously provided) 3-0P-201 cautions & note before step 6.1.2.9 & step (including version/revision number)_6".,., 1.".2'"."-9-"0"'3,.1 1,,3!!..12"'0"'0"'9

'-_________

_ Proposed references to be pro vided to applicants during examination

None Learning Objective: 6902121A Obi. 9c (As available)

Question Source: Bank # Modified Bank # New ==:c-(Note changes or attach parent) X Question Hi story: Last NRC Exam (Optional: Questions valid ated al t he f acility since 10195 will generally un d ergo less n'gorous review by the NRC; fa ilure to provide the in f omlarion will necessitate a detailed review of every question.) Question Cognitive Le vel: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Ana l ysis 55.41 55.43 7 x 06/25/2009 Turkey Point ILC 25 NRC Examination Question 31

Unit 3 is in Mode 6.

The crew is preparing to drain the refueling cavity to the RWST.

One RHR Pump is running. What effect will fully opening 3-887, RHR to RWST Hdr Isol Valve, have on the RHR System? Flow indicated on FI-3-605 , RHR Hx Outlet Flow Indicator, will (1) . Flow to the core will (2) (1) (2) A decrease remain the same B decrease decrease C Increase remain the same 0 Increase decrease Page 61 of 200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 3 1

Unit 3 is in Mode 6.

The crew is preparing to drain the refueling cavity to the RWST.

One RHR Pump is running. What effect will ful l y opening 3-887, RHR to RWST Hdr 1501 Valve , h ave on the RHR System? Flow indicated on FI-3-60S, RHR Hx Outlet Flow Ind icator, w ill (I) . Flow to the core will (2) (J) (2) A decrease remain the same B decrease decrease C Increase remain the same D Increa se decrease Page 6 1 o f 200 Question 31 KIA 005A4.05 Residual Heat Removal 0612512009 Turkey Point ILC 25 NRC Examination Ability to manually operate and/or monitor in the control room: Position of RWST recirculation valve (locked when not in use, continuously monitored when in use).

Reference:

5613-M-3050 sheet 1 3-0P-201 CAUTIONS and NOTE before step 6.l.2.9 and step 6.1.2.9 Per the cautions, cavitation may occur. This flowpath robs flow from 605, decreasing flow to core and indicated flow will also decrease.

Question history: New Correct answer: B A Incorrect; flow to the core decreases. Plausible; FCV 605 will open in attempt to restore core flow and need to realize where FI-3-605 is in flowpath.

B Correct; flow is robbed from FI-3-605 and from the core. C Incorrect; FI-3-605 does not increase and flow to the core decreases.

Plausible; if tap were after 605, indicated flow would increase. FCV-3-605 will open in attempt to restore core flow. Need to realize where FI-3-605 is in flowpath D Incorrect; FI-3-605 does not increase.

Plausible; if tap were after 605 , indicated flow would increase and need to realize where FI-3-605 is in flowpath.

Cognitive level: 2 Need to determine effect of opening 3-887 and apply that to where valve is in system flowpath Page 62 of 200

Question 31 KIA 005A4.05 Residual Heat Removal 06/25/2009 Turkey Point IL C 25 NRC E xam inati o n Abi li ty t o m a nually o pe rate and/or m onito r in the co ntr o l room: Position of R WST recircu l atio n va l ve (locked w h en n o t in use , continuously m o nit o r e d when in u se).

Reference:

56 13-M-3050 s h eel I 3-0P-20 1 CAUT IO NS a nd NOTE before ste p 6.1.2.9 a nd step 6.1.2.9 Per the cautions , cav it at i on ma y occ ur. This fl ow path r obs fl ow fr o m 605, decreasing fl ow 10 co re and indicated fl ow w ill al so decrea se. Que s ti o n hi story: New Correct answer: B A In correc t; flow to the core de creases. Plau si ble; FCV-3-605 will open in a tt e mpt to r estore co r e fl ow an d need to reali z e w h e r e FI-3-605 is in fl ow p a th. 8 Co rre ct; fl ow i s robbed from FI-3-605 a nd fro m the co re. C I ncorrec t; FI-J-60S does n ot increase a nd flow to the core decreases.

Plausible; if t a p w er e after 605, indicated flow would in crease. FCV-3-60s wi ll ope n in attempt to restore co r e fl ow. Need to rea li ze w he re FI-3-60S i s in fl ow path o In co rr ect; FI-3-60S d oes n o t increase.

Pl aus ibl e; if tap were after 605 , indicated flow wo uld increase and ne ed to reali ze w here FI-3-605 i s in fl ow p ath. Cogn iti ve l eve l: 2 Need t o dete rmin e effect of ope nin g 3-887 a nd apply that to w her e va l ve i s in sys t e m fl ow p ath {)a ge 62 of 200 Question #32 ES-401 Question 32 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional)

Per reference , order i s LCs , HHSI & RHR , then ECCs RO 2 1 006A3.05 3:L Technical Reference(s)

5614-T-L 1 Sheet 12 & 12A 12/21/1996 6/25/2009 Form ES-401-5 SRO ----(Attach if not previously provided), __________________

_ (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective:

6902157 Obi. 8.b (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Opt i onal: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of eveIY question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X This is a substitute KIA. The original KIA (006A3.08) is not applicable to PTN.

Qu es tion #32 ES-401 Question 32 Writt en Examination Question Worksheet Exam i nat i on Outline Cross-Reference

Level Tier# Group # KIA # Importance Rating Proposed Question: See atta c hed Proposed Answer: C Explanati o n (Opti o nal): P er r efe r e n c e , o rd er i s L Cs. HHSI & RHR , th en E CCs RO 2 1 006A3.05 -1L Te c hnica l Reference (s): 5614-T-L 1 Sheet 12 & 12A 12/21/1996 6/25 12 0 09 Form ES-401-5 SRO ----(Atta c h if not p rev iously prOvided)...,-

_________________

_ (I ncluding v ers i on/revision number) ___________________

_ Prop o sed references to be provided to applicants during examination

None Learning Obje c ti v e: 6902 1 5 7 Obi. 8.b (As available)

Question Source: 8ank# Modified Bank # New __ ,,-(Note changes or attach parent) X Question History: La s t NRC Exam (Op t ional: QUestions valida t e d a lth e facility since 10195 w ill generally undergo le ss ri g orous review b y the N RC; failure 10 provide the information will necessi t a t e 8 d e tail e d rev i ew o f ev e ry qu e sti on.) Quest io n C o gnitive Le v el: 10 CFR Part 55 Content: C o mment s: Memory or Fundamental Knowledge Comprehension or Anal y sis 55.41 _7_ 55.43 X This is a s ubstitute KiA. The original KJA (00SA 3.08) is not app l icable to PTN.

06/25/2009 Turkey Point ILC 25 NRC Examination Question 32 Unit 4 has received a LOOP/LOCA. Which one of the following correctly lists the order for sequencer loading? A Load Centers ECCs RHR and HHSI Pumps B RHR and HHSI Pumps ECCs Load Centers C Load Centers RHR and HHSI Pumps ECCs D RHR and HHSI Pumps Load Centers ECCs Page 63 of 200 *

06/25/2009 Turke y P oint IL C 25 NRC Examinati o n Que s tion 32 Unit 4 ha s recei ved a LOOP/LO CA. Which one of the foll ow ing co rre ct l y li s t s th e order f or se qu e ncer lo ading? A Load C enter s ECCs RHR and HHSI Pump s B RHR and HHSI Pum ps ECCs L oa d Ce nter s C Load Centers RHR a nd HHSI Pump s ECCs o RHR a nd HHSI Pump s Load C ent ers ECCs Page 63 o f 2oo 06125/2009 Turkey Point ILC 25 NRC Examination Question 32 KIA 006A3.05 Emergency Core Cooling Ability to monitor automatic operation of the Emergency Core Cooling System, including:

Safety injection pumps NOTE: This is a substitute KIA

Reference:

5614-T-Ll sheets 12 & 12A Per reference, order is LCs, HHSI & RHR, then ECCs Question history: New Correct answer: C A Incorrect per reference.

Plausible; need to know order B Incorrect per reference.

Plausible; need to know order. C Correct per reference.

o Incorrect per reference.

Plausible; need to know order. Cognitive level: 1 Page 64 of 200 06/25/2009 Turke y P oi nt IL C 25 NRC Exa min a ti on Que s t ion 32 KJA 006A3.05 Emergency Co r e Coo lin g A bilit y to moni t o r a ut o m a t ic o perati o n o f th e Emergenc y Core Coo li ng Sys tem , i ncludin g: Safety inje c ti o n pump s NOTE: This is a s ub s titute KIA R ef er ence: 56 14-T-L1 s h eets 1 2 & 1 2A P c r r efe r e n c e , o rder i s L es, HH S I & RHR , then ECCs Q u es ti o n hi s t o r y: N e w Co rrect answe r: C A In co rr ect per refere n ce. P l ausib l e; need to know o rder B In correc t per ref e ren ce. Pl a u s ible; need t o kn ow order. C Co rrect per r efere n ce.

0 In correct per r efe ren ce. Plau s ible; n eed t o kn ow o rd e r. Cogni ti ve l eve l: I

Pa ge 64 of200 Question #33 ES-401 Question 33 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional):

Technical Reference(s):

0-ADM-536 section 3.5.1 02/18/2009 (Attach if not previously provided) 3-0P-064 step 4.4 4/2/09 RO 2 1 006K6.02 6/25/2009 Form ES-401-5 SRO (including version/revision

________ _ T.S.3.5.1 Proposed references to be provided to applicants during examination:

None Learning Objective: 6902121b Obi. 9a (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to prov i de the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 --x

Question #33 ES-401 Question 33 Written Examination Question Worksheet E xamination Outline Cross*Reference

Le vel Tier # Group # KIA # Imp o rtance Rating Proposed Question:

See attached Proposed Answer: D Explanalion (Optiona l): Technical Reference(s):

O-ADM-53S section 3.5.102/18/2009 (Attach i f not previously provided) 3-0P-064 step 4.4 4 12/09 612512009 Form ES-401-5 RO SRO _2_ 1 --00SKS.02 -.-:ill!.... (including version/revisi on number),.-B""D:o-O"P""'-0"'S"'4c.1"2,,1-'-17,,,,1"'2"'0,,0-'-7

_________

_ T.S.3.5.1 Proposed references to be provided to app licants during examination:

None Learnin9 Objective: S902121b Obi. 9a (As available)

Question Source: Bank # Modified Bank # New __ (Note changes or attach parent) X Question Hi story: L ast NRC Exam (Optional: Questions valid ated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the infonnation w ill necessitate 8 detailed re view of every question ,) Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x 06125/2009 Turkey Point ILC 25 NRC Examination Question 33 Unit 3 is at 100% with the following 3A Safety Injection (SI) Accumulator values: Level -6560 gallons Pressure -670 psig Boron concentration

-1925 ppm The discharge MOV breaker is locked open Which ofthe following correctly states the status of the 3A SI Accumulator and the basis for that status? The 3A SI accumulator is ... A OPERABLE.

All Tech Spec and admin limits have been met. B INOPERABLE.

There is insufficient water to ensure core reflood during a large break LOCA. C INOPERABLE.

The cover gas pressure would cause the introduction of nitrogen into the RCS following a large break LOCA. D INOPERABLE.

The boron concentration is insufficient to ensure all areas ofthe core will remain subcritical during the reflood foHowing a large break LOCA. Page 65 of 200 06/25/2009 Turkey P o int lL C 25 NRC Examination Question 33 Unit 3 is at J 00% wi th the f o ll owi n g 3A Safety In jection (S I) Accum ul ator va lu es: Le vel -6560 ga li o n s >> Pre ssu r e -670 psig };o Boron conce ntrati o n -1 925 ppm );> The di sc h a rge MOV breaker i s l ocke d o pen W hi ch of the fo ll ow in g correc t ly s t ates the s tatu s of th e 3A S I Acc umulator and th e basis fo r that s t at u s? The 3A SI acc umul a t or i s ... A OPERABLE. A ll Tech Spec and a dmin lim its h ave been m et. B I NO PERABL E. Th e r e is in s uffi c ient water to e n su r e co re refl ood during a lar ge break LOCA. C I NOPERAB LE. The cover gas pre ssure wo uld ca u se the introduction of nitr ogen into t h e R eS foll ow ing a l a r ge br eak LO eA o I NO P ERA BL E. T h e b oron co n ce nt rat ion i s in s uffi c i ent t o ensure a ll a reas of th e co r e will r ema in subc riti c al during the r e flo o d foll owi n g a l a r g e break LOCA. Pag e 65 of 200 06/2512009 Turkey Point ILC 25 NRC Examination Question 33 KJ A 006K6.02 Emergency Core Cooling Knowledge of the effect of a loss or malfunction on the following will have on the Emergency Core Cooling System: Core flood tanks (accumulators)

Reference:

T.S.3.5.1 0-ADM-536 section 3.5.1 3-0P-064 step 4.4 BD-OP-064 Question history: New Correct answer: D A Incorrect; boron is too low. B Incorrect; level limits are 6552-6788 gallons. Plausible; near lower limit and that is basis for level. C Incorrect; pressure limits are 600-675. Plausible; near upper limit and that is basis for upper limit D Correct lAW 0-ADM-536.

Cognitive level: 1 Page 66 of 200 *

06/25/2 0 0 9 Turk ey P o int IL C 25 NRC Exa minati on Q u est i o n 33 KIA 0 06 K 6.02 E m e r ge n cy Core Coo lin g Kn ow l e d ge of t h e ef f ec t of a l oss o r ma l fu n c ti o n o n t h e f o ll o wing w ill h ave o n t h e E m e r ge n cy Co r e Coo lin g Sys t e m: Co r e fl ood tank s (a cc umul a t ors) R efe r e n ce: T.S. 3.5.1 0-A D M-S36 sec ti o n 3.5.1 3-0P-06 4 ste p 4.4 B D-O P-06 4 Question h is t o r y: New Correci answ er: D A In co rr ec t; b oron i s to o l ow. B In co rr e ct; l eve l lim i t s a r e 6552-6788 ga ll o n s. Pl a u s ibl e; n ear l ow er limit a nd that i s b as i s f or l eve l. C In co rr ec t; p r ess ur e l i mi ts a r e 60 0*675. Pl a u s ibl e; n c ar upp e r limit and th at i s b as i s fo r upp er limi t o Co rr ect L AW O-AD M-536. Cogn iti ve l eve l: I Page 66 of 200 Question #3 4 ES-401 Question 34 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: A Explanation (Optional)

6/25/2009 Form ES-401-5 RO SRO 2 1 --007G2.2.40 4.7 T.S. 3.4.4 action a requires closing block valve if excessive leakage action e sys 3.0.4 is not applicable O-ADM-536

p. 54 if greater than 10 gpm requires closing block Technical Reference(s)

..:...T;.::

.S::.:...-=3:.:....4.:..:..4...:.-.

_______________

_ (Attach if not previously provided) 0-ADM-536

p. 54 02/18/2009 (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

T.S. 3.4.4 Learning Objective:

6902109 Obi. 12.e (As available)

Question Source: Bank# 1.1.28.24.3

.10 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 x *

Qu es ti o n #34 ES-401 Question 34 Written Examination Question Worksheet Examination Outline Cross-Reference

L evel Tier# Group # KIA # Im portance Rating Proposed Question: See attached Pr o posed Answer: A Explanation (Optional): 6 12 5 1 2 0 09 Form ES-401-5 RO SRO 2 --1 --007G2.2.40 ..M.. ....iL T.S. 3.4.4 a c tion a r e quire s cl osi n g bl o d va l ve i f excess i v e l ea ka ge a c li o n e sys 3.0.4 i s n o t a pp li ca bl e O-A DM-53 6 p. 5 4 if g r ea ter than 1 0 g pm r e quir es cl os in g bl o ck Te c hnical Reference (s): "T.,.,.

_______ _ (Attach if not pre v i o us l y pro v ided) 0-ADM-536

p. 54 02118/2009 (including v ersion/revision number) __________________

_ Proposed references to be pr o vided to applicants during exam i nation: T.S. 3.4.4 Learning Objective: 6902109 Ob i. 12.e (As available)

Question Source: Bank# Modified Bank # New 1.1.28.24.3.10 __ ;-;-(Note changes or attach pa r ent) Questi o n History: Last NRC E x am (O pl ion a l: Questions v alidated at t he facili t y since 10195 will gen e rally undergo tess rigorous review by t he N RC; failure to provide the i n f ormation w ill nec e ssit a t e a de t ail e d revie w o f ev e ry ques t ion.) Question Cogniti v e Le v el: 10 CFR Part 55 Content Comments: Memory or Fundamental Knowledge C o mprehension or Anal y sis 55.41 55.43 10 x

. Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Item: 1.1.28.24.3.10 9021240310

Unit 3 is operat i ng in Mode 3 preparing to startup the reactor.

The temperature indicator downstream of the pressurizer PORVs alarms.

Subsequent leakrate calculations determine that PORV-3-456 has 12.0 gpm leakage past its seat.

ReS leakrate was 0.03 gpm and has gone to 12.03 gpm. What actions are required by Technical Specifications? (Reference provided)

A) Startup (entry into Mode 2) is permitted. The associated bock valve is required to be closed since the PORV is inoperable. 8) Startup (entry into Mode 2) is permitted. The associated bock valve may be closed if desired but it is not required by Tech Specs. C) Startup (entry into Mode 2) is NOT permitted until the PORV is repaired. The associated bock valve is required to be closed since the PORV is inoperable. 0) Startup (entry into Mode 2) is NOT permitted until the PORV is repaired.

The associated bock valve may be closed if desired but it is not required by Tech Specs. CORRECT or INCORRECT feedback for item: 1.1.28.24.3.10 T.S. 3.4.4 action a requires closing block valve if e x cessive leakage. ADM 536 p. 54 -if> 10 gpm requires closing block action e says 3.0.4 not applicable Item Classification

Application Item d i fficulty:

0.00 Keywords: 010 G2.1.12 Item weight: 10 Points required for mastery: 1 Correct alternative (s): A Judging values of alternatives

A=1 8=-1 C=-1 0=-1 Ifems in G:\Trng\Apps\WEXAM INE\PTN Exam\PTN Exam.xam Item: 1.1.28.24.3.10 9021240310

Unit 3 is operating i n Mode 3 preparing to startup the reactor.

The temp erature indicator downstream of the pressur izer PORVs alarms.

Subsequent Jeakrale calculations determine that PORV-3-456 has 12.0 gpm leakage past its seat.

ReS leakrate was 0.03 gpm and has gone to 12.03 gpm. VVhat actions are required by Technical Specifications? (Reference provided) A) Startup (e ntry into Mode 2) fs permitted , The associated bock valve is required to be closed since the PORV is inoperable. B) Startup (entry into Mode 2) is permitted. The associated bock valve may be c losed if desired but it is not required by Tech Specs. C) Start up (entry into M ode 2) is NOT permitted until the PORV is repaired_ The associated bock valve is required to be closed since the PORV is inoperable , 0) Startup (entry into Mode 2) is NOT permitted until the PORV is repaired. The associated bock valve may be closed jf desired but it is not required by Te ch Specs. CORRECT or INCORRECT feedback for item: 1.1.28.24.3.10 T.S. 3.4.4 action a requires closing block valve if excessive leakage. ADM 536 p. 54 -if > 10 gpm requires closing block

action e says 3.0.4 not applicable

....,;'em Classification

Application Item difficulty

0.00 Keywords: 010 G2.1.12 Item weight: 10 Points required for mastery; 1 Correc t alternative(s

): A Judging values of alternat i ves: A=1 6=-1 C=-1 0=-1 0612512009 Turkey Point ILC 25 NRC Examination Question 34

Unit 3 is in Mode 3.

PR T temperature, pressure, and level are increasing.

It is determined that PORV PCV-3-456 has 12.0 gpm leakage past its seat. What actions are required by Tech Specs? Tech Spec 3.4.4 provided as reference.

Entry into Mode 2 is ... A permitted.

The associated block valve is required to be closed since the PORV is inoperable.

B permitted.

The associated block valve may closed if desired but it is not required by Tech Specs. C NOT permitted.

The associated block valve is required to be closed since the PORV is inoperable.

D NOT permitted.

The associated block valve may closed if desired but it is not required by Tech Specs. Page 67 of 200 06/25/2009 Turkey PoinllLC 25 NRC Exa mination Question 34

U nit 3 i s in Mode 3.

PRT t em p e ratur e, pre ss ure , a nd l eve l are in cr e as ing.

I t is d c t c nnin ed that POR V r eV-3 A S6 h as 1 2.0 gpm l eakage pa s t it s sea t. What actions a re required b y Tech S p ecs? T ec h Spec 3.4.4 provided as reference. Entry int o M o de 2 i s ... A permitted.

The associated bl oc k va l ve i s r e quir ed t o be clo se d s in ce the PORV is inoperable.

B perrnitled.

Th e associated bl oc k va l ve m ay closed if desired but it i s n o t requir ed by Tech Specs. C NO T pennitted.

The associated bl oc k va l ve i s r e quired t o b e closed s in ce th e POR V is in o p e r ab l e. o NO T pcnnitted. Th e associated blo ck va l ve m ay closed if desired but it i s n o t required b y Te c h S p ecs. Page 67 of200 0612512009 Turkey Point ILC 25 NRC Examination Question 34 KJA 007G2.2.40 Pressurizer Relief/Quench Tank Ability to apply Technical Specifications to a system

Reference:

T.S. 3.4.4 action a requires closing block valve if excessive leakage 0-ADM-536

p. 54 if greater than 10 gpm requires closing block action e sys 3.0.4 is not applicable History: EXAMINER 1.1.28.24.3.10 Correct answer: A A Correct per above reference B Incorrect; closure required.

Plausible; need to know at what point closure is required.

C Incorrect; entry into Mode 2 permitted since 3.0.4 not applicable.

Plausible; Mode entry is usually not permitted.

D Incorrect; per above discussion.

Plausible; need to know at what point closure is required and realize Mode change permitted.

Cognitive level: 3 Have to apply Tech Specs Note: Provide T.S. 3.4.4 Note: PTN has no T.S. that apply directly to the PRT; only the piping into and the piping going out. Page 68 of 200 06/25/2009 Turkey Point ILC 25 NRC Examination Que s ti on 3 4 KIA 007G2.2.40 Pressuriz e r Relief/Quench Tank Abi lit y to app l y Tec hni cal Specifications to a system

Reference:

T.S. 3.4.4 action a require s closing b l ock va l ve if excessive leakage O*AOM*536

p. 54 if greater than J 0 !Pm r eq u ires closing block act i on e sys 3.0.4 i s n o t applicable Hi s tory: EXAM I NER 1.1.28.24.3.10 Correct answer: A A Co rrect per above ref e r ence B Incorre c t; closure required.

Plau s ible; need to know at what point closure is required.

C Incorrect; entry into Mode 2 permitted s ince 3.0.4 not app li cable. Plau s ibl e; Mode entry i s usually not permitted. o In correct; per above discussion.

Plausible; need t o know at what point closure is required and realize Mode change permitted.

Cogn i tive level: 3 Have to apply Tech Specs Note: Provide T.S. 3.4.4 Note: PTN has no T.S. that apply directl y to the PRT; on l y the piping into and th e piping going out. Pag e 68 of 200 Question #35 ES-401 Question 35 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: B Explanation (Optional):

RO 2 1 008K4.07 6/25/2009 Form ES-401-5 SRO 3D 4kV bus feeder breakers 3AB19 and 3AD06 feed power to the swing bus for CCW Technical Reference(s)

5610-T-L1 sheets 138,141,142 , & 143 (Attach if not previously providedi-)

___________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

Learning Objective: (As available)

Question Source: Bank# 1.1.24.38.6

.50 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x

Ques t ion #35 ES-401 Written Examination Question Workshe e t Question 35 Examination Outline C ross-Reference

L evel Tier # Group # KIA # Imp ortance Rating Pr oposed Question:

See attached Proposed Answer: B E xp lanation (Op tional): RO 2 1 008K4 , 07 6 12 5/2009 Fo r m ES-401-5 SRO 3 D 4kV bu s feede r breakers 3AB 1 9 and 3AD06 reed power to the sw in g bus ror CCW Technical Reference(s

): 5610-T-L1 sheets 1 38, 141 , 142 , & 143 (Attac h i f not previously

____________

_ (includ ing ve r sion/rev i sio n number) __________________

_ Proposed references to be provid ed to appl ica nts during examinatio n: Learning Objective: (As available)

Question Source: Bank # 1 , 1 , 24 , 38,6 , 50 Modified Bank # __ ;:-(Note changes or a tt ach parent) New Questio n History: Last NRC E x am (Optional: Questions v alidated at the facility s i nce 10195 will generally undergo less rigorous review by the NRC: failure to prov i de the information will necessitate a detailed review of every question.)

Question Cognitive Le vel: 10 CFR Pa rt 55 Content: Comments: Memory or Fundamental Know l edge Comprehens i on o r Analysis 55.41 55.43 7 x Items inG:\ Trng\,A.QPs\WEXAMINEXPTNExam\PTN-e x am.xam Item: 1.1.24.38.6.50 9021380650; Operators are attempting to energize 3D 4kV bus from the 38 4kV bus. Which ONE of the following describes the interlock between 3D 4kV bus feeder breakers 3AB19 and 3AD06? A) 3AB19 must be closed first. 3AD06 will trip if 3AB19 is opened. B) 3AD06 must be closed first. 3AB19 will trip if 3AD06 is opened C) 3AB19 must be closed first. 3AD06 will remain closed if 3AB19 is opened. 0) 3AD06 must be closed first. 3AB19 will remain closed if 3AD06 is opened. Item Classification

Comprehension Item difficulty:

0.00 Keywords: NLOCT, SNPO, NPO , LOCT, NSO Item weight: 10 Points required for mastery: 1 Correct alternative(s):

B Judging values of alternatives

A=-1 B=1 C=-1 0=-1 Memo Field:

REFERENCE:

5610-T-L1 Sh 142 OL: 100 lIems in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN E x am.xam It em: 1.1.24.38.6.50 .021380650; are attempUng t o energize 3D 4kV bus from the 3B 4kV bus. VVhich ONE of the f o llowing describes the interl ock between 3D 4kV bus feeder b r eakers 3AB19 and 3AD06? A) 3A819 must be closed fi r st. 3A006 will t rip jf 3A819 is opened. 8) 3ADOS m u st be closed first. 3AB19 will trip jf 3ADOS is opened C) 3AB19 must be closed first. 3AD06 w ill remain closed if 3AB19 is opened. D) 3AD06 mu st be closed first. 3AB19 will remain closed if 3AD06 is opened. Item Classification

Comprehension Item difficulty

0.0 0 Keywo rd s: NLOCT , 8NPO , NPO , lOCT , NSO Item weight 10 P oints required for mastery: 1 Correct alternative(s

): B Judging values o f alternatives

A=-1 8=1 C=-l 0=-1 M emo Field:

REFERENCE:

5610-T*L 1 8h 142

OL: 100

06/25/2009 Turkey Point ILC 25 NRC Examination Question 35 Which one of the following describes the operation of 3D 4kV bus feeder breakers 3AB 19 and 3AD06? Note: 3AB 19 is 3B Bus Supply to 3D Bus 3AD06 is Feeder to 4.16 kV Bus 3B A 3AB 19 must be closed first. 3AD06 will trip if 3AB 19 is opened. B 3AD06 must be closed first. 3AB 19 will trip if 3AD06 is opened. C 3AB 19 must be closed first. 3AD06 will remain closed if 3AB 19 is opened. D 3AD06 must be closed first. 3AB19 will remain closed if3AD06 is opened. Page 69 of 200

06/25/2009 Turke y Point IL C 25 NRC Examinat i o n Que s tion 35 Whi c h o n e o f the followin g d escribes the opera ti on of30 4kV bus feeder breakers 3AB 19 a nd 3AD06? No t e: 3AB 1 9 i s 3B Bu s Supp l y t o 3 D Bus 3A D 06 i s Feeder to 4.16 kV Bu s 3B A 3AB 1 9 mus t b e c l osed fir s t. 3AD06 w ill trip i f3AB I 9 is opene d. B 3 AD06 must be cl ose d fir s t. 3AB 19 w ill trip if3AD06 i s ope n ed. C 3AB 1 9 mu st be closed fir s t. 3A D06 wi ll remain clo se d if 3 ABI9 i s ope ned. o 3AD06 mu s t b e clo se d fir s t. 3AB 19 w ill rem ain closed if 3 AD06 i s opened . Pa ge 69 o f 200 06/2512009 Turkey Point ILC 25 NRC Examination Question 35 KJ A 008K4.07 Component Cooling Water Knowledge of the Component Cooling Water System design features and/or interlocks which provide for the following:

Operation of the CCW swing-bus power supply and its associated breakers and controls

Reference:

5610-T-Ll sheets 138, 141, 142, & 143 3D 4kV bus feeder breakers 3AB 19 and 3AD06 feed power to the swing bus for CCW Question history: EXAMINER 1.1.24.38.6.50 Correct answer: B A Incorrect; per reference, 3AD06 must be closed first. Plausible; need to know which breaker must be closed first. B Correct; this describes the interlock.

C Incorrect; 3AD06 must be closed first. Plausible; need to know which breaker must be closed first. o Incorrect; 3AB 19 will trip if 3AD06 is opened. Plausible; need to know that 3AD06 opening will trip 3AB 19. Cognitive level: 1 Page 70 of 200 * *

06/25/2009 Turkey Point IL C 25 NRC Exa minati o n Q u estio n 35 KIA 008K4.0 7 Compon ent Coo lin g Water Knowledge of th e Co mpon e nt Coo ling Water Sys tem design feature s and/or interl oc k s which pro vide fo r th e following:

Operation of th e CCW sw in g-bu s power s upply a nd it s assoc i a t ed breakers and co ntrol s R efere n ce: 5610-T-LJ shee t s 1 38, 141 , 14 2 , & 14 3 3 D 4k V bus f eeder br eake r s 3AB 19 and 3AD06 feed po we r to the sw in g bus for CC W Question hi story: EXAM I NE R 1.1.24.38.6.50 Cor rect answer: B A In co rr ec t; p er reference.

3A D0 6 must be closed first. Plau s ible; n eed t o know which br ea ker mllst b e closed first. B Correct; thi s describes the int e rl ock. C In co rr ec t; 3AD06 mu st b e closed first. Plau s ibl e; n eed to kn ow which br ea k e r mu st b e closed tirst. D In correct; 3AB 1 9 will trip if 3AD06 i s opened. Pl aus ibl e; need to kno w that 3AD06 open ing w ill trip 3AB 1 9. Cogn itive l eve l: I Page 7 0 of 200 Question #36 ES-401 Question 36 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: A Explanation (Optional):

RO 2 1 010K2.04 Technical Reference(s):

3-0NOP-003.6 Enclosure 1 06/27/2008 6125/2009 Form ES-401*5 SRO (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective:

6902163 Obi. 4 (As available)

Question Source: Bank # Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional.

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X

Queslion #3 6 ES-401 Q uest i on 36 W ritten E xa m i nat i o n Qu es tion Wor k sh e e t Examination Outline Cross-Reference

L evel Tier# Group # KIA # I mportance Rating Proposed Question: See attached Proposed Answer: A Explanation (Optional)

RO 2 1 010K2.04 Technical Reference(s

): 3-0NOP-003

.6 Enclosure 1 06/27/2006 6/2 5 1 2009 Form E S-401-S SRO (Attach if not previously provided)".-

_________________

_ (including version/revision number) _______________

_____ _ P r oposed references to be provided to applican t s during exami n atio n: No n e Learning Objective: 6902 1 63 Obj. 4 (As available)

Question Source: Bank # Modi f ied Bank # New ==:;-(Note changes or attach parent) X Question H istory: L ast NRC E xam (Optional: Questions validateci at th e facility since 10195 w ill generally undergo less rigorous review by the NRC: fa ilure t o provide the infomalion will necessita te a detailed review o( every question.)

Question Cognitive L evel: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X 06/2512009 Turkey Point ILC 25 NRC Examination Question 36 The red label on TI-3-467, Safety Tailpipe Temperature, means it is powered from ... A 3P06 B 3P07 C 3P08 D 3P09 Page 710[200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 36 The red lab e l on Tf-3A67 , Safety Tailpipe Temperature, means it is powered from ... A 3P06 B 3 P 07 C 3P08 D 3P09 *

P age 7 1 of200 06125/2009 Turkey Point ILC 25 NRC Examination Question 36 KIA OI0K2.04 Pressurizer Pressure Control Knowledge of bus power supplies to the following:

Indicator for code safety position

Reference:

3-0NOP-003.6 Enclosure 1 Question history: New Correct answer: A A Correct B Incorrect; power is 3P06. Plausible; need to know P07 is white C Incorrect; power is 3P06. Plausible; need to know P08 is blue D Incorrect; power is 3P06. Plausible; need to know P09 is yellow Cognitive level: 1 Page 72 of 200 * *

06125/2009 Turkey Point IL C 25 NRC Examination Question 36 KIA 010K2.04 Pressurizer Pres s ure Contro l Knowledge of bus power supplies to th e following:

Indicator for code safety position

Reference:

3-0NOP-003.6 Enclosure 1 Que s tion history; New Correct answer: A A Co rrect B In correct; p ow er i s 3P06. Plausible; need to know P07 is white C Incorrect; power i s 3P06. Plau s ible; need to know POS is blue o Incorrect; power i s 3P06. Plausible; need to know P09 i s yellow Co!,rnitive level: I Pa ge 72 of 200 Question #37 ES-401 Question 37 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 2 1 --010K4.02 Technical Reference( s): =56=-1:,:-,0::...-

-T..:...-...=O:;....-...:..16=..;B=-..=.0....:.;4/c...;.1..;:;.9:...:::/9'-=6

__________

_ (Attach if not previously provided)

_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X *

Que s tion #37 ES-401 Question 37 Written Examination Question Worksheet Examination Outline Cross-Refe r ence: Le vel Trer# Group # KIA # I mportance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Option al): 6 12 5/200 9 Form ES-401-5 RO SRO 2 --1 --010K4.02 .2JL ..M.... Technical Reference(s)

,!:56",1",Oc.-

_________ _ (Attach if not previously provided)-,-

___________

______ _ (i nclud ing version/revision number) ________________

____ _ Proposed references to be provided to applicants during examination

None Learning Objective: (As available)

Question Source: Bank# Modified Bank # N ew __ :;-(Note changes or attach parent) X Question Histo ry: La st NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provi de the i nformat io n will necessitate a detailed review of every quest ion.) Question Cognitive Leve l: 10 CFR P art 55 Content: Comments: Memory or Fu ndamental Knowledge Comprehension or Analysis 55.41 55.43 7 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 37 What are the setpoints for the Pressurizer Backup Heaters energization (1) and Letdown isolation (2)? (1) ill-A 2210 psig 12% B 2210 psig 14% C 2220 psig 12% 0 2220 psig 14% Page 730[200 * *

06/25/2009 Turkey P o int ILC 25 NRC Examination Question 37 What are the se lp o i n l s for the Pr essurize r Backup He aters energization (1) and Letdown isolation (2)? (I) A 2210 psig 1 2% B 2210 psig 14% C 2220 psig 12% D 2220 p s i g 14% P age 73 o f 200 06125/2009 Turkey Point ILC 25 NRC Examination Question 37 KIA 010K4.02 Pressurizer Pressure Control Knowledge of Pressurize Pressure Control design features and l or interlocks which provide for the following:

Prevention of uncovering PZR heaters

Reference:

5610-T-D-16B Question history: New Correct answer: B A Incorrect; LID isolation is 14%. Plausible; 12% is manual SI setpoint B Correct per above reference

-B/U heaters energize at 2210 psig and LID isolates at 14%. C Incorrect; BIU heaters energize at 2210 psig and LID isolates at 14%. Plausible; 2220 is setpoint for control group full on and 12% is manual SI setpoint.

D Incorrect; B I U heaters energize at 2210 psig. Plausible; 2220 is setpoint for control group full on. Cognitive level: 1 Page 74 of 200

06/25/2009 Turkey P o i n t IL C 25 NRC Exa mination Quest i on 37 K! A 0 I OK4.02 Pr ess u rizer Pre ssu re Co ntrol Kn ow led ge of P r ess u rize Pr essure Con t rol design features a nd/or in terloc k s whic h pro vide fo r the fo ll owi n g: Pre vent i o n of uncovering PZR he aters

Reference:

5610-T-D-1 6B Q u es ti o n hi s t ory: New Correct answer: 8 A In correct; U D i so l at i on i s 14%. 1 2% i s manual SI sC lp o i n! B Co rr ect per above reference

-B IU heat e r s ene r g i ze a t 221 0 p s ig and LI D i so l a tes a t 1 4%. C In co rr ect; B IU h ea t e r s energ i ze at 22 1 0 p s i g and U D i so l ates a t 1 4%. Plau s ible; 2 220 is sClpoi n! fo r co ntr o l group full on a nd 1 2% i s m an u a l S l se tpoint. D In co rr ec t; B I U h eate r s e n ergize at 22 1 0 p s i g. Pl aus ibl e; 2220 i s sc lp o i n l f o r co ntr o l group full o n. Cogni ti v e le v e l: 1 P age 74 of2oo Question #38 ES-401 Written Examination Question Worksheet Question 38 Examination Outline Cross-Reference

Proposed Question:

See attached Proposed Answer: B Explanation (Optional)

4D01 breaker 38 goes to RTB and Bypass A 4D23 breaker 12 goes to RTA and Bypas s B Level Tier # Group # KIA # Importance Rating RO 2 1 012K1.02 Technical Reference(s)

4-0NOP-003.4 p. 3 of 3 09/14/2008 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided) 4-0NOP-003.5 Attachment 3 p. 2 of 209/14/2008 (including version/revision number) __________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902163 Obi. 4 & 8 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _6_ 55.43 X

Question #38 ES-401 Writt e n Examinat i on Question Worksheet Question 38 Examination Ou tlin e Cross-Reference

Proposed Question:

See attached Proposed Answer: B E x planation (Option al): 4DOI breaker 38 goes t o RTB and Bypa ss A 4023 breake r 12 goes to RTA and Bypa ss B L evel Tier # Gro up # KIA # Im portance Rating RO 2 1 012K1.02 Technical Reference (s): 4-0NOP-003.4 Attachmenl 3 p. 3 of 3 09/14/2008 6 125/2009 Form ES-401-5 SRO (Att a ch if not previously provided) 4-0NOP-003.5 Attachment 3 p 2 of 2 09/14/2008 (includi ng ve r sion/revision number) ______________

____ _ Proposed references to be provided to applicants during examinatio n: N one L earning Objective: 6902 1 63 Ob i. 4 & 8 (As available) Question Source: Bank # Modified Bank # N ew _-,-:;-(Note changes o r attach parent) X Question H is t ory: Last NRC E x am (Optional: Questions validated at the fa cility since 10/95 will generally undergo less rigorous review by the NRC; fa ilure t o provide the information will necessi tate a detailed review of every question.)

Question Cognitive Lev el: 10 CFR Part 55 Content: Comme n ts: Memory or Fundamental Knowledg e Compre h ension or Ana l ysis 55.4 1 _6_ 55.43 x Question #39 ES-401 Question 39 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: C Explanation (Optional)

RO 2 1 012K2.01 Technical Reference(s)

3-0NOP-003.7 Enclosure 1 p. 2 of 306/27/2008 6/2 5/2009 Form ES-401-5 SRO (Attach if not previously provided) 3-0NOP-003.8 p. 2 of 306/27/2008 (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 690260 Obi-2 (As available)

Question Source: Bank # 1.1.24.63.5.9 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional: Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to prov i de the infonnation w i ll necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 7 55.43 x

Question #39 ES-401 Q ues t io n 3 9 Writt en E x am i nat i on Q ues t ion Work s h e et Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: c Explanation (Optiona l): RO 2 1 012K2.01 ..li. Technical Reference(s)

3-0NOP-003.7 Enclosure 1 p. 2 of 3 06/27/2008 6/2512009 Form ES-4 0 1-5 SRO ----.lL (Attach if not previously provided) 3-0NOP-003

.8 Enclosure 1 p. 2 of 3 06/27/2008 (including version/revision nu m ber) __________________

_ Proposed references to be provided to app l icants during examination:

None L earning Objective: 690260 Obi. 2 (As available)

QUestion Source: Bank# Modified Bank # New 1.1.24.63.5.9 ==;;-(Note changes or attach parent) Question History: Last NRC Exam (Optional:

Ouestions validated at the facility since 10195 will generally undergo less rigorous review by the N RC; f ailure t o provide the i nformat ion will necessitate a detailed review of every question.)

QUestion Cognitive Level: 10 CFR Part 55 Content Comments: Memory or Fundamental Knowledge Comprehension or Ana l ysis 55.41 _7_ 55.43 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.63.5.9 9021630509

The bottom two rows of reactor protection bistable postage stamp lights have gone out. This could be due to the loss of what instrument bus? A) 3P06 8) 3P07 C) 3P08 D) 3P09 CORRECT or INCORRECT feedback for item: 1.1.24.63.5.9 RCO Group 19 Audit Exam 3-0NOP-003.8, 5610-T-O-2 Item Classification:

Knowledge Item difficulty

0.50 Keywords:

012 K2.01 Item weight: 10 Points required for mastery: 1 Correct alternative(s):

C Judging values of alternatives:

A=-1 8=-1 C=1 D=-1 Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.63.5.9 9021630509:

Th e bottom two rows of reactor protection bistable postage stamp lights have gone out. This cou ld be due to the loss of what inst rum ent bus? A) 3P06 B) 3P07 C) 3POB 0) 3P09 CORRECT or INCORRECT feedback for item: 1.1.24.63.5.9 RCO Group 19 Audit Exam 3-0NOP-003,B

, 5610-T-O-2 Item Classification

Knowledge Item difficulty

0.50 Keyv.rords

012 K2.01 Item weight: 10 Points required for mastery: 1 Correct altema t ive(s): C Judging values of alternatives

A=-l 8=-1 C=1 D=-l *

06125/2009 Turkey Point ILC 25 NRC Examination Question 38 Initial conditions:

Unit is in Mode 2 at 2% power.

Train 4B RPS testing is in progress.

The 4B Reactor Trip Bypass Breaker is racked in and closed. Subsequently:

125V DC Bus 4DOI is lost. What is the status of the reactor trip breakers and will the reactor trip as a direct result of the 4DO I failure? A Only the 4A Reactor Trip Breaker will open. The reactor will NOT trip. B Only the 4B Reactor Trip Breaker will open. The reactor will NOT trip. C The 4A Reactor Trip Breaker and 4B Reactor Trip Bypass Breakers will open. The reactor will trip. D The 4B Reactor Trip Breaker and 4B Reactor Trip Bypass Breakers will open. The reactor will trip. Page 75 of200 *

06/25/2009 Turkey Point ILC 25 NRC Examination Question 38 Initial conditions:

Unit is in Mode 2 at 2% power.

Train 48 RPS testing is in progress.

The 48 Reactor Trip Bypass Breaker is racked in and closed. Subsequently:

1 25V DC Bus4DOI i s l ost. What is the status of the reactor trip breakers and will the reactor t rip as a direct r esult of the 4D01 fai l ure? A Only the 4A Reactor Trip Breaker will opcn. The reactor wi ll NOT trip. B Only the 48 Reactor Trip Breaker will opcn. The reactor wi ll NOT trip. C The 4A ReaclOr Trip Breaker and 48 Reactor Trip Bypass Breakers wi ll open. D T h e reactor will trip. The 48 Reactor Trip Breaker and 48 Reactor Trip Bypass Breakers will open. The reactor will t rip . PlIge 75 or 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 38 KJA 012K1.02 Reactor Protection Knowledge of the physical connections and/or cause-effect relationships between the Reactor Protection System and the following system: 125V dc system

Reference:

4-0NOP-003.4 Attachment 3 p3 of 3 4001 breaker 38 goes to RTB and Bypass A 4-0NOP-003.5 Attachment 3 p2 of2 4023 breaker 12 goes to RTA and Bypass B History: New Correct answer: B A Incorrect; 4001 goes to RTB & BYP A. Plausible; need to know power supplies.

B Correct; 4001 goes to RTB & BYP A -reactor trip will not occur. Plausible; need to know power supplies.

C Incorrect; 4001 goes to RTB & BYPA. Plausible; need to know power supplies.

o Incorrect; 4001 goes to RTB & BYP A. Plausible; need to know power supplies.

Cognitive level: 2 Need to compare lost power supply to reactor trip breakers and determine effect on plant for conditions given. Page 76 of 200

06 1 25 1 2009 Turkey P o int lLC 25 NRC Exam inati on Question 38 KIA 012KI.02 Reactor Protection Knowledge of the physical connect i o ns a nd/or cause*effect relationships between the Reactor Protection Sys tem and the following system: 125V de syste m

Reference:

4-0NOP-003.4 Attac hm en t 3 p3 of 3 4001 breaker 38 goes to RTB and Bypass A 4-0NOP-003.5 Attac hm en t 3 p2 of2 4D23 breaker 1 2 goes to RTA and Bypass B Hi story: New Correct answer: B A In correct; 4001 goes to RTB & BYPA. Plausible; need to know power supp lie s. B Co rr ect; 4001 goes to RTB & BYPA -reactor trip will not occur. Pl ausib le; need to know power supplies.

C Incorrect; 400 1 goes t o RTB & BYPA. Plausible; need to know power supplies.

o In correc t; 4001 goes to RTB & BYPA. Plausible; need to know power supp li es. Cognitive l evel: 2 Nee d to compa r e l ost power sup pl y to re acto r trip breakers and detenninc effec t on plant for conditions given. Page 7 6 of 200 0612512009 Turkey Point ILC 25 NRC Examination Question 39 Unit 3 is at 100% power when the following occurs:

Multiple annunciators simultaneously alarm.

The top two rows of bistable lights on VPB go out. Which one of the following procedures should the crew implement?

A 3-EOP-E-0, Reactor Trip or Safety Injection B 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS C 3-0NOP-003.7, Loss of 120V Vital Instrument Panel 3P07 D 3-0NOP-003.S, Loss of 120V Vital Instrument Panel 3POS Page 77 of 200 06/25/2009 Turkey Point ILC 25 NRC Examination

Question 39 Unit 3 is at 100% power when the following occurs:

Multiple annu n ciators simulta n eously a l ann.

The top two rows of bistable lights on VPB go o ut. Which one of the following procedures should the crew implement?

A 3-EOP-E-O , Reactor Trip o r Safety Inj ect i on B 3-EOP-FR-S.

I , Response to Nuclear Power GenerationlATWS C 3-0NOP-003.7 , Loss of 120V Vital Instrument Panel 3P07 D 3-0NOP-003.8 , Loss of 120V Vital Instrument Panel3P08 Page 77 of 200 Question 39 KIA 012K2.01 Reactor protection 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge of bus power supplies to the following:

RPS channels, components and interconnections

Reference:

3-0NOP-003.7 Enclosure 1 page 2 of 3 3-0NOP-003.S Enclosure 1 page 2 of 3 Question history: EXAMINER 1.1.24.63.5.9 modified Correct answer: C A Incorrect; loss of one train on RPS/SI only , no need for reactor trip. Plausible; need to realize that loss of 3POS takes out two trains of bistable lights. B Incorrect; loss of one train on RPS/SI only , no need for reactor trip and not in ATWS. Plausible; need to realize that loss of 3POS takes out two trains of bistable lights. C Correct; per ONOP-003.7 Enclosure 1, lose two rows of bistable lights. D Incorrect; loss of 3POS causes loss of bottom two rows of bistable lights. Plausible; lo s s of 3POS causes loss of bottom two rows of bistable lights. Cognitive level: 2 Candidate needs to diagnose loss of 3P07 from information given and then determine what procedure to use Pag e 78 o f 200 * *

Question 39 KIA 012K2.01 Reactor protection 06/25/2009 Turkey Point IL C 25 NRC Examination Knowledge of bus power s uppli es to the fo ll owi ng: RPS c hannel s, compone n ts and interconnect i ons

Reference:

3-0NO P-003.7 Enclosure I page 2 of 3 3-0NOP-003.8 Enclosure I page 2 of 3 Question history: EXAM I NER 1.1.24.63.5.9 modified Co r rec t answe r: C A lo ss of one train on RPS/S I only, no ne ed for rea cto r trip. Plau s ible; need to rea li z e that l oss ofJP08 takes o ut two trains of bistable light s. B In correc t; lo ss of one train on RPS/S l only, no need for rea c tor trip and not i n ATWS. Plau s ible; need to rea l ize that lo ss of3P08 takes out two trai n s of bi s table li ghts. C Correc t; per ONOP-003.7 Enclosure I , J ose two rows o f bistable light s . o Inc o rr ect; Joss of3P08 causes loss of bottom tw o rows of bistable lights. Plausible; lo ss of3P08 causes l oss of bottom two rows of b i sta ble li ghts. Cogn iti ve le ve l: 2 Ca ndidat e need s to diagnose loss of3P0 7 from inf ormatio n given and then determine what procedure to use Page 78 of 200 Question #40 ES-401 Question 40 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: D Explanation (Optional):

6/25/2009 Form ES-401*5 RO SRO 2 --1 013A2.01 LOCA on other unit only starts HHSI Pumps on unaffected unit. 4-EOP-E-O Attachment 3 step 9 will stop the Unit 3 HHSI Pumps if both Unit 4 Pumps are running Technical Reference(s)

4-EOP-E-0 Att. 3 step 9 12/09/2008 (Attach if not previously provided) 5613-T-L 1 Sheet 12A 10103/1996 (including versionlrevision number), ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902163 Obi-11 (As available)

Question Source: Bank # Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional: Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 X

Question #40 ES-401 Written Examination Question Worksheet Question 40 Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: D Explanation (Optional):

RO 2 _1_ 013A2.01 6/2512009 Fonn ES-401-5 SRO LOCA on o ther unit o nly s t a rt s HH S I Pumps on unaffected unit. 4-EOP-E-O Anachmenl 3 step 9 will s top the U nit 3 HH S I Pumps if both Unit 4 Pumps are running Technical Reference(s)

4-EOP-E-0 Att. 3 step 9 12/09/2008 (Attach if not previously provided) 5613-T-L1 Sheet 12A 10/03/1996 (includin g version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902163 Obi. 11 (As available)

Question Source: Bank # Modified Bank # New -:-:c=:;-(Note changes or attach parent) X Question History: Last NRC Exam (Optional: Questions validated a t the facilify since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every quesl/on.) Question Cognitive Le ve l: 10 CFR Part 55 Content: Comments: Memory o r Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 X

................ , .... 06/25/2009 Turkey Point ILC 25 NRC Examination Question 40

The 3A , 3B, and 4A HHSI Pumps are running.

MOV-3-843A and B, HHSI Cold Leg Injection Valves , are both closed.

The 3A and 3B RHR Pumps are NOT running. The event is a safety injection on Unit (1) . The Unit 3 HHSI Pumps will be operated in accordance with (2) , Reactor Trip or Safety Injection.

(1) (2) A Unit 3 3-EOP-E-O B Unit 3 4-EOP-E-0 C Unit 4 3-EOP-E-0 D Unit 4 4-EOP-E-0 Pag e 7 9 of 200 06/25/20 09 Turke y P o int IL C 25 N R C Examination

Question 40

The 3A. 3 8 , and 4A HH S I Pump s are runnin g.

MOV-3-843A and B , HH S I Co ld L eg Inj ection Valves , are b o th clo sed.

Th e 3A and 3 8 RHR Pump s are NOT runnin g. The eve nt is a safe t y injection o n Un it (I) . The Unit 3 HH S I Pump s will be o p e r at ed in accor d ance wi th (2) , R eac tor Trip or Safety In jec tion. (I) (2) A Un it 3 3-EOP-E-O B U nit 3 4-EO P-E-0 c Uni t 4 3-EOP-E-0 D Uni t 4 4-EOP-E-0

P age 79 of 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 40 KIA 013A2.01 Engineered Safety Features Actuation Ability to (a) predict the impacts of the following malfunctions or operations on the Engineered Safety Features Actuation System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

LOCA

Reference:

5613-T-Ll Sheet 12A LOCA on other unit only starts HHSI Pumps and EDGs on unaffected unit 4-EOP-E-0 Attachment 3 step 9 will stop the Unit 3 HHSI Pumps ifboth Unit 4 Pumps are running -or one pump if only one Unit 4 HHSI Pump is running. Question history: New Correct answer: D A Incorrect; per above discussion.

Plausible; HHSI Pumps are running on Unit 3. B Incorrect; per above discussion.

Plausible; HHSI Pumps are running on Unit 3. C Incorrect; per above discussion. Plausible; might expect to stop Unit 3 Pumps using a Unit 3 procedure.

o Correct per above discussion.

Cognitive level: 1 Page 80 of 200 *

06/25/2009 Turkey Point IL C 25 NRC Examination Question 40 KIA 0J3A2.0 1 Engineered Safety Features Actuation Ability to (a) predict the impacts of the following malfunctions or operat i o n s on the Engineered Safe t y Features Actuation System; and (b) ba se d on those predictions , u se procedures t o correc t , contro l , or mitigate the consequences of tho se malfunctions or operatio n s; LOCA

Reference:

56J3-T-LJ Shee t 12A LOCA on other unit only starts HHSI Pump s and EDGs on unaffected unit 4-EOP-E-O Attachment 3 step 9 will s top the Unit 3 HH SI Pumps ifboth Unit 4 Pumps arc running-or one pump ifon l y one Unit 4 HHS I Pump is running. Question history: New Correct answer: D A In correct; per above discussion.

Pl a u s ibl e; HHSI Pumps arc running on Unit 3. B I ncorrect; per above discussion. Plau s ible; HHSI Pumps are rurming on Unit 3 . C In correct; per above di sc u ss ion. Plau si ble; might expec t to stop Un it 3 Pumps using a Unit 3 procedure.

o Correct per above discussion.

Cognitive l evel: 1 Page 80 o f 200 Question #41 ES-401 Question 41 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: c Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 2 1 --022K1.04 4-NOP-030 Limitation 2.2.3.6 lists components for "rule of 5." NCCs count as one load; each ECC is a load; each RHR HX is a load. 4-0SP-203.1 Attachment 5 p. 5 -only 2 NCCs running/4-0SP-203.1 Attachment 7 p. 7 -MOV-4-1417 (CCW to NCC inlet) closes/4-0SP-203.2 p 16 -MOV-4-1418 closed (CCW from NCC) closes CCW not aligned to RHR HX until enter 4-EOP-ES-1.3. Technical Reference(s):

3-NOP-030 2.2.3.6 03/11/2009 (Attach if not previously provided) 3-0SP-203.1 Att. 5 & 7 11/19/2008 (including version/revision number) 3-0SP-203.2 Att 5 & 7 04/08/2009 3-EOP-E-0 Att. 3 04/09/2009 Proposed references to be provided to applicants during examination:

None Learning Objective: (As available)

Question Source: Bank# 1.1.24.40.3

.13 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _8_ 55.43 x

Qu es tion #41 ES-401 Question 41 Written Examination Question Worksheet E x aminat i on Outl i ne Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Pr o posed Answer: C E x planation (Opt i onal): RO 2 _1_ 022K1.04 6/25 12 009 Form ES-401-5 SRO 4-NO P-030 Limi ta ti o n 2.2.3.6 li s t s co mp o n e nt s f o r " rule o f 5." NCCs co unt as o n e l o ad; eac h E CC is a l oad; e a c h RHR H X is a l oa d. 4-0 S P-203.1 A tt ac hm e nt 5 p. 5 -o nly 2 NCCs r unn i n g/4-0S P-2 0 3.1 A ll.e hment 7 p. 7 -M O V-4-141 7 (CC W to NCC inl e t) c1 os es/4-0S P-20 3, 2 A rt ac hm e nt 7 p 1 6 -MO V-4-1418 clos ed (CC W fr o m NCC) cl o s e s CCW n o t a li g n ed t o RHR HX u n t il ent e r 4-EO P-E S-1.3. Te c hnical Ref e r e nee (s): 3-NOP-030 2.2.3 ,6 0 3/11/2009 (Attach if not pre v iousl y provided) 3-0SP-203 , 1 Atl. 5 & 7 11/19/20 0 8 (including ve r sion/revisi o n number) 3-0SP-2 0 3.2 Att 5 & 7 04/08/2009 3-EOP-E-0 Att. 3 04/0 9/2009 Propo s ed referen c e s to be provided to applicants during e x amination: None Learning Objective: (As available) Quest io n Sou r ce: Bank # M o dified Bank # New 1.1.24.40.3.13 -,,-,--;;-

(Note c hanges or attach parent) Qu e stion History: Last NRC Exam (Opt i ona l: Qu e stions valida/ed a/ t he f acility since 10195 w ill g enerally und e rgo l ess rigoro u s revie w b y the NRC; failure t o provide the informa t ion will necessita t e a detailed re vi e w o f every ques ti on.) Que s tion C o gniti v e Le v el: 1 0 CFR Part 55 C o ntent: Co mments: Memory o r Fundamental Knowledge C omprehension or Anal y sis 55.41 _8_ 55.43 x Items in G:\Trn\J\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.40.3.13 9021400313 he following events occurred when Unit 3 was operating at 100% with all systems in normal alignment.

An AUTO SI signal occurred.

All systems functioned as designed.

Sequencing has just completed. Which ONE of the following identifies the number of CCW load(s) attached to the CCW system as i t relates to the CCW " Rule of Five"? A) Two CCW loads 8) Three CCW loads C) Four CCW loads D) Five CCW loads CORRECT or INCORRECT feedback for i tem: 1.1.24.40.3.13 5613-T-L 1 SH 1 2A18 " A" AND "C" ECCs ("8" does not auto start) Item Class i fication: Analysis Item difficulty

0.50 Keywords: 008 A3.08 , LOP , NLOCT em weight: 10 oints requi r ed for mastery: 1 Correct alternative (s): A Judging values of alt e rnatives: A=1 8=-1 C=-1 0=-1 Memo Field:

REFERENCE:

OP-030 P/L; SO-040 Component Cooling Water System; OPS APPROVED T.S. 3/29/04 Items in G:\Tmg\Apps\WEXAMINE\PTN Exam\PTN Exam.x am Item: 1.1.24.40.3.13 following events occurred when Un it 3 was operating at 1 00% with a ll systems i n normal alignment.

An AUTO SI signal occurred.

All systems functioned as designed.

Sequencing has just com pleted. VVh i ch ONE of the following identifies the number o f CCW load(s) attached to the CCW sys tem as it re l ates to the CCW "Rule of Five"? A) Two CCW loads B) Thre e CCW loads C) Four CCW loads D) Five CCW loads CORRECT or INCORRECT feedback for Item: 1.1.2 4.4 0.3.13 5613-T-L 1 S H 12MB "A" AND "C" ECCs ("8" does not auto start) Item Classification

Analysis Item diffi c ulty: 0.50 Keywo r ds: 008 A3.0a. LOP. NLOCT em weight: 10 oints required for mastery: 1 Correct allernative(s)

A Judging values of alternatives:

A=1 8=-1 C=-1 0=-1 Memo Field:

REFERENCE:

OP-030 P i L;80-040 Component Cooling Water System: O PS APPROVED T.S. 3129/04

06/25/2009 Turkey Point ILC 25 NRC Examination Question 41

Unit 3 has experienced a spurious safety injection.

The RO has just commenced performance of 3-EOP-E-0 , Attachment 3 , Reactor Trip or Safety Injection, Prompt Action Verifications.

RCPs are running. How many CCW loads will be attached to the CCW System as it relates to the "Rule of 5" before the BOP commences Attachment 3 and after Attachment 3 has been completed?

Before After A Two Two B Three Three C Two Three 0 Three Four Pag e 81 of 200

06/25/2009 Turkey Point ILC 25 NRC Examination Question 41

Unit 3 has experienced a s purio u s safety inject i on ,

The RO has just commenced performance oF3-EOP-E-O , Attachment 3 , Reactor Trip or Safety I njection , Prompt Action Verifications.

Rep s are run n ing. H ow many CCW loads will be attached to the CCW System as it re l ates to the "Rule of 5" before the BOP commences Attachmen t 3 and after Attachment 3 has been c ompleted?

Before A Two Two B Three Three c Two Three D Three Four Pa ge S I of 2 00 Question 41 KJA 022K1.04 Containment Cooling 06/25/2009 Turkey Point ILC 25 NRC Examination Knowledge of the physical connections and/or cause-effect relationships between the Containment Cooling System and the following system: Chilled water

Reference:

3-NOP-030 Limitation 2.2.3.6 lists components for "rule of 5." NCCs count as one load; each ECC is a load; each RHR HX is a load. 3-0SP-203.1 Attachment 5 p. 5 -only 2 NCCs running 3-0SP-203.1 p. 7 -MOV-4-1417 (CCW to NCC inlet) closes 3-0SP-203.2 p 16 -MOV-4-1418 closed (CCW from NCC) closes 3-EOP-E-0 -NCCs started by Attachment 3 ifRCPs are running Question history: Examiner 1.1.24.40.3.13 Correct answer: C A Incorrect; NCCs started by Attachment

3. Plausible; need to realize NCCs are started for conditions in stem B Incorrect lAW above discussion.

NCCs isolated and 2 ECCs running. Plausible; we have 3 ECCs, but only 2 start because of rule of 5. C Correct lAW above discussion. NCCs isolated and 2 ECCs running initially and NCCs started by Attachment

3. o Incorrect lAW above discussion.

Only 2 ECCs running initially.

Plausible; we have 3 ECCs. Cognitive level: 2 Need to realize what CCW loads are in rule of 5 and then apply that loads in service after SI actuation and again after completion of Attachment

3. Page 82 of 200

Question 41 KIA 022KI.04 Co ntainment Coo lin g 06/25/2009 Turkey P o int IL C 25 NRC E xa min a ti o n Knowledge o f the physical co nn ec ti ons a nd/o r ca u se*effec t r elat i ons hip s b e tween the Co nt a irunent Coo ling System and the f o ll owi n g sys tem: C hilled water R e ference: 3*N OP*0 30 Limit a tion 2.2.3.6 li sts co mp o nent s for " rul e of 5." NCCs count as one lo a d; each ECC i s a load; each RHR H X i s a l oa d. 3-0S P-20 3.1 A ttachmenl 5 p. 5 -o nly 2 NCCs running 3-0SP-203.1 A tta c hment 7 p. 7 -MOV-4-1417 (C C W to NCC inlet) c lo ses 3-0 S P-203.2 Attachment 7 p 16 -MOV-4-1418 closed (CCW IT o m NCC) closes 3-EO P-E-O Attachment 3 -NCCs s t a rted b y Attachment 3 ifRCP s are running Question hi story: Exa min er 1.1.24.40.3.1 3 Correct answer: C A In co rrect; NCCs s tarted b y Attachment

3. Pl a u s ibl e; n ee d to r ea lize NCCs a re start ed for co nditi o n s in s t e m B In correct l AW above di sc u ss ion. NCCs i so lated and 2 ECCs running.

we ha ve 3 ECCs , but o nly 2 s tart bec a u se o f rule ofS. C Correct l AW a b ove di sc u ss i o n. NCCs i so l a t e d and 2 ECCs running initiall y and NCCs sta rt ed by A tta chme nt 3. D In co rre c t l A W ab ove discussion.

On ly 2 ECCs running initiall y. Pl a u s ible; we ha ve 3 ECCs. Cogn iti ve le ve l: 2 Need t o r ea li ze w h a t CCW lo a d s are in rul e of 5 and then a ppl y that l oads in serv ice aft er S I actuat i o n a nd aga in after co mpletion of A ttachment 3 . P age 82 of200 Question #42 ES-401 Question 42 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

RO _2_ 1 022K3.02 6/25/2009 Form ES-401*5 SRO S/G level uses a wet reference leg t-.P indicator.

The compares the pressure of the full reference leg to pressure of the variable leg. The variable leg represents the mass in the S/G. As the Containment temperature lowers, the density in the reference leg increases.

The variable leg density is not significantly affected.

At I25°T Containment temperature, the indicated level will be less than actual (than it will be at 110°F). This means that at 110°F Containment temperature, there is more mass in the S/G. Technical Reference(s)

5613-M-3074 Sheet 3 04/09/2009 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

__ Learning Objective:

6902321 Obi-6 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X Point Beach NRC exam given on 6113/07 question 41 -significantly modified Question #42 ES-401 Question 42 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KlA# Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optio nal): 6/2512009 Form ES-401-5 RO SRO 2 --1 022K3.02 S/G l eve l use s a wet reference leg LlP indicator. The compa re s th e pressure of the full reference l eg to pres s ure of the variable l eg. The var i ab l e l eg r epresents the mass in the S/G. As the Co ntainm en t temperature lo wers , t h e dens it y in the reference l eg increases.

T he variab le l eg density is not sign ifi can tl y affec t ed. A t 125°T Co nt ain m ent temperature , th e indicated l evel will be les s than actual (than it will be at II O C F). Thi s mean s that at !IO C F Con t ainmen t temperature , there is more ma ss in the S/G. Technical Reference(s)

5613-M-3074 Sheet 3 04/09/2009 (Mach if not previously pr ov ided)-,-_______________

_ (incl uding versio n lrevis ion number) ____________________

_ Proposed references to be provided to applicants during examination:

--"N",o"-n,,,e,-

__ Learning Objective: 6902321 Obj. 6 (As avai l able) Question Source: Bank # Modified Bank # New __ ::-(Note changes or attach parent) X Question History: Last NRC E xa m (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC: failure to provide the information will necessitate 8 detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X Point Beach NRC exam given on 6 113/07 question 41 -significan tl y modified 0612512009 Turkey Point ILC 25 NRC Examination Question 42 Initial conditions

Unit 4 Containment temperature at 110°F

All Steam Generator levels on program at 60% Subsequent!

y:

CCW flow to the NCCs is lost.

Containment temperature has increased to 125°F

All Steam Generator levels on program at 60% Steam Generator secondary system mass with the Containment at 125°F is (1) than at 110°F. This is because the (2) leg density has decreased.

(1) (2) A less variable B less reference C greater variable 0 greater reference Page 83 of 200 06/25/2009 Turkey Point IL C 25 NRC Examination Question 42 Initial conditions

Un it 4 Co ntaimn ent temperature at 110°F

All Steam Generator l eve l s on program at 60% Subsequently:

CCW flow to the NCCs is lost.

Containment temperature has increa s ed to 12 5°F

All Steam Generator l evels on program at 60% Steam Generator secondary system mass with the Containment at 125°F i s (1) than at 1 10°F. Thi s is because the (2) leg density has decreased. (I) (2) A less variab l e B I\!ss Tl!fcrcm.:e C greater variable D greater reference Page 83 of200 Question 42 KJ A 022K3.02 Containment Cooling 06125/2009 Turkey Point ILC 25 NRC Examination Knowledge of the effect that a loss or malfunction of the Containment Cooling System will have on the following:

Containment instrumentation readings

Reference:

5613-M-3074 sheet 3 S/G level uses a wet reference leg indicator.

The compares the pressure of the full reference leg to pressure of the variable leg. The variable leg represents the mass in the S/G. As the Containment temperature lowers, the density in the reference leg increases.

The variable leg density is not significantly affected.

At 125°T Containment temperature, the indicated level will be less than actual (than it will be at 110°F). This means that at 125°F Containment temperature, there is less mass in the S/G. Question history: Point Beach NRC exam given on 6113107 question 41 -significantly modified Correct answer: B A incorrect; per above discussion, variable leg not significantly affected.

Plausible; variable leg also inside containment.

B correct per above discussion C incorrect; per above discussion, mass has decreased and variable leg not significantly affected.

Plausible; need to analyze how change in reference leg pressure will affect S/G mass. o incorrect; per above discussion, mass has decreased.

Plausible; need to analyze how change in reference leg pressure will affect S/G mass. Cognitive level: 2 Candidate needs to analyze effect on change in reference leg temperature on mass in S/G. Page 84 of 200

06/25/2009 Turk ey P o int IL C 25 N RC Examination Q ue st ion 42 KIA 0 22 K 3.02 Co ntainment Coo ling Kn ow ledge o f th e effect that a lo ss or malfun c tion of the Con tainment Coo ling System will ha ve on th e f o llo w in g: Co ntainmenr instrumentation reading s

Reference:

56 J 3-M-3074 s he e t 3 S/G l evel uses a wet r e f e r e n ce leg 8 P indicator.

TIle co mpares the pre ss ure of the full refe rence leg t o pre ss ure of the vari able l eg. The variab l e leg r e pr ese nt s the ma ss in the S/G. As the Co nt a inment temperature Jower s, the den si t y in the referen ce leg in c rea s e s. The varia ble l eg den s it y i s n o t s ignifi ca ntl y affected.

At 1 25°T Co ntainment t e mperature, the indicated l eve l will be le ss than ac tual (than it w ill b e at 11 0°F). Thi s mean s that at 125°F Co ntainment temper a ture , there i s l ess ma ss in th e S/O. Question hi s tor y: Point B eac h NRC exam gi v en on 6/1 3/07 qu es ti on 41 -s ignificantl y modified Correct answer: B A inc o rr ec t; per ab ove discussion, variable le g n o t s i gnificantly affected.

Plau s ibl e; va ri a ble l eg a l so in s ide containment.

B correct per above di scussio n C incorrect; per above discussiun , mas s has lIccrea s cd and va riable leg nut signifil:a ntl y affected.

Plau s ible; need to a nal yze how ch a n ge in referen c e leg pr ess ure will affect S/O ma ss. o in correc t; per above di sc u ss i on , mas s ha s d ecre a se d. Pl a u s ible: need to analyze how change in r eference le g pre ss ur e w ill affect S/G mass. Cogn iti ve le ve l: 2 Ca ndidate n ee d s 1 0 analyze effect o n cha ng e in r efere n ce l eg tempe r a tur e on m ass in S/G. P age 84 of200 (t Question #43 ES-401 Question 43 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

RO 2 1 026A3.01 6/25/2009 Form ES-401-5 SRO 20# signal opens 880A & B and sends signal to sequencer to start CSPs. Sequencer will start CSPs if SI not reset. Feedwater Isolation verification is step 3 of Attachment

3. SI is reset in step 12. Technical Reference(s):

5614-T-L 1 sheet 12A 10/21/1996 (Attach if not previously provided) 5610-T -L 1 sheet 11 04/09/2009 (including version/revision number) 4-EOP-E-0 Att. 3 12/09/2008 Proposed references to be provided to applicants during examination:

None Learning Objective:

6902125 Obi. 7.d (As available)

Question Source: Bank# Modified Bank # New 1.1.26.21.3.6

___ (Note changes or attach parent) Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x Q u es ti o n #43 ES-4D1 Question 43 Written Examination Question Worksheet Examination Outline Cross-Referen c e: Level Tier# Group # KIA # Importance Rating Propo s ed Question: See attach e d Pr o posed A nswer: A E x planation (Optional): RO 2 1 026A3.01 6 125/2 00 9 Form ES-4Dl-5 SRO 20# s i g n a l o p e n s 880A & B a n d se n ds s i g nal t o se qu e nc e r t o s tart CS P s. Se qu e n c er w ill s t a rt CS Ps i r S I n OI r ese t. Fee dw a t er I so l a ti o n ve rificati on i s s t e p 3 o r A tt ac hm e nt 3. S I i s re s e t in s t e p 1 2. T ec hni c al Reference (s): 5614-T-L 1 she e t 12A 10/21/1996 (A tta c h if n o t previou s l y pro vi ded) 5610-T-L 1 sheet 11 04/0 9/2 0 09 (i n c luding v er si on/revision number) 4-E O P-E-0 AH. 3 12/09/2008 Prop o sed references t o be pr o vided to app li cant s during e x amination: None Learning Objecti v e: 6 902125 Obi. 7.d (As available)

Question Sour c e: Bank# Modi fi ed Bank # New 1.1.26.21.3.6 __ ,,-(Note c hanges o r attach parent) Questi o n Hist ory: Last NR C E x am (Optional: Questions validated at t he facility since 10195 will gen e rall y undergo less rigorous review by t he NRC; failure to pr o vide t he i nform a tion will necessi t a t e a d e t ailed rev i e w of every qu e stion.) Question Cogn i tive L e vel: 10 C FR Part 5 5 Content: Comment s: Memo ry or Fundamental Knowledge Comprehensi o n o r Analysis 55.41 55.4 3 7 x 06/2512009 Turkey Point ILC 25 NRC Examination Question 43

Unit 4 experienced a LOCA.

The BOP is verifying Feedwater Isolation in accordance with 4-EOP-E-0, Attachment 3, Reactor Trip or Safety Injection, Prompt Action Verification, when Containment pressure exceeds 20 psig. How will the Containment Spray Pumps (CSPs) and their discharge valves (MOV-4-880 A & B) respond? A The CSPs will start. MOV-4-880 A & B will open. B The CSPs will start. MOV-4-880 A & B will NOT open. C The CSPs will NOT start. MOV-4-880 A & B will open. D The CSPs will NOT start. MOV-4-880 A & B will NOT open. Page 85 of 200 *

06/25/2009 Turke y Point IL C 25 NRC Examinat i o n Question 4 3

Un it 4 ex p e ri enced a LOeA.

The BOP is verifyi n g Feedwater I solation in accordance wit h 4-EOP*E-O , Attach m ent 3, Reactor Trip o r Safety Inj ec ti on , Pr ompt Act i o n Verifica ti on , when Conta inm e nt pressure exceed s 20 psig. H ow will th e Conta inm ent Spray Pumps (CS P s) and th eir d i sc h a r ge valves (MOV-4-880 A & B) respond? A The CS Ps w ill start. MOV 880 A & B will open. B The esps w ill start. MOV-4-8 80 A & B will NOT open. C The esps wi ll NOT start. MOV-4-880 A & B w ill open. o The esps w ill NOT start. MOV-4-880 A & B wi ll NOT open . Page 85 o r 2 0 0 06/25/2009 Turkey Point ILC 25 NRC Examination Question 43 KIA 026A3.01 Containment Spray Ability to monitor automatic operation of the Containment Spray System, including:

Pump starts and correct MOY positioning

Reference:

5614-T -L1 sheet 12A -20# signal opens 880A & B and sends signal to sequencer to start CSPs. 5610-T -L1 sheet 11 -sequencer will start CSPs if SI not reset. 4-EOP-E-0 -Feedwater Isolation verification is step 3 of Attachment

3. SI is reset in step 12. Question history: EXAMINER 1.1.26.21.3.6 Correct answer: A A correct per above discussion.

B Incorrect; the 880s will open. Plausible; SI signal has already been generated.

C Incorrect; the CSPs will start. Plausible; if SI had been reset, CSPs would not start. D Incorrect; see discussion for B and C Cognitive level: 2 Need to realize that SI not reset yet , so CSPs will start and MOYs will open. Page 86 of 200

06/25/2009 Turke y Point IL C 25 NRC Exami n ation Question 43 KiA 026A3.01 Co ntainm e nt Spray Ability to m o nitor au tomatic o peration of the Co ntainment Spray System, includ in g: Pump s tart s and correct MOV positioning

Reference:

56 1 4-T-L I s heet 1 2A -20# s ignal opens 88 0A & B a nd sends s ignal t o sequencer to s tart es p s. 56 1 0-T-LJ s heet 11 -se quen ce r will start CS P s ifSI n o t reset. 4-EOP-E-O Attachment 3 -Feed w ater Isolation verification i s ste p 3 of Attachment

3. SI i s re se t in s tep 1 2. Ques ti on hi story: EXAMINER 1. 1.26.21.3.6 Correc t answer: A A co rrect per above di sc u ss ion. B In co rr ec t; the 88 0 5 will open. Plausible; SI signa l ha s already been generated. C In co rre ct; the CS P s wi ll s t art. Pl a u s ible; irSI had be e n re set , CSPs would not s tart. D In correc t; see di scuss i on for Band C Cog niti ve le v el: 2 Nee d to realize that S I not r ese t yet, so CS P s will s tart and MOVs will open . Page 86 of 200 Question #44 ES-401 Question 44 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: C Explanation (Optional):

6125/2009 Form ES-401-5 RO SRO 2 --1 039A1.05 This is a classic steam line leak. A dilution would cause Tavg to increase.

ADM-200 5.4.3.7 requires for a secondary transient , to reduce power below 100% using steam demand/turbine load. Technical Reference(s)

0-ADM-200 5.4.3.7 03/26/2009 (Attach if not previously provided)-:--

________________

_ (including version/revision number), ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902025 Obi. 5 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 H.B. Robinson NRC exam given on 6/26/07 question 16 -modified X

Q ue s tio n #44 ES-401 Question 44 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level T ier# Group # KJA# Importance Rating Proposed Question: S ee attached Propo se d Answer: C E x planation (Optional): RO 2 1 039A1.05 6/25 12 009 Form ES-401-5 SRO This i s a classic s t eam l i ne le ak. A di lu tion wo uld ca u se Tavg to in crea se. A DM-200 5.4.3.7 r e quire s for a seco nd a r y tran s i e nt , t o reduce po wer below 10 0% u s ing s te am demand/turbine l oad. Te ch nical Reference(s)

0-ADM-200 5.4.3.7 03/26/2009 (Attach if not previousl y provided),, _________________

_ (including version/revision number) ____________________

_ Propo s ed refer e n ce s to be provided t o applicants du r ing examination

None Learning Objective:

6902025 Obi. 5 (As avai l able) QUestion Source: Bank # MOdified Bank # __ ,.,-(Note changes or attach parent) New X Question History: Last NRC E x am (Optional:

Questions valida ted althe facility since 10195 will generally undergo less rigorous review by the NR C; failure 10 provide th e in f ormation will necessitate a detailed review of every question.) Q uesti o n Co gniti ve Level: 1 0 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comp r ehension or Analysis 55.41 55.43 5 H.8. Robin so n NRC exam g i ve n on 6/2 6/07 question 1 6 -modifi e d X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 44

Unit 3 is at 100% power.

The RO has recently perfonned a dilution to compensate for fuel burnup.

The following indications are noted in Control Room: Power Range Nls are increasing slowly. Tavg is decreasing slowly. Reactor power is 100.3% and rising slowly. Which one of the following describes the event in progress and the action required in accordance with 0-ADM-200, Conduct of Operations?

A Excessive RCS dilution Reduce power by reducing turbine load. B Excessive RCS dilution Reduce power by inserting control rods. C Main steam line leak Reduce power by reducing turbine load. D Main steam line leak Reduce power b y inserting control rods. P a g e 8 7 of 200

06/25/2009 Turkey Point IL C 25 NRC Examinat i o n Ques t ion 44

Unit 3 is at 1 00% power.

Th e RO has recently performed a dilu t i o n to compe n sate for fuel humup.

The following indication s are noted in Cont r o l Room: >> Power Range N i s are increa s ing s l ow l y. >> Tavg is decrea s ing s l ow l y. >> Reactor power i s 100.3% and rising s l ow l y. Whic h one of the following de scri be s the eve nt in pr ogress and the action required in acco rd ance w ith O-ADM-200, Conduct of Operat i ons? A Exces s i ve ReS dilution Redu ce power b y reducing turbi n e l oad. B Excessive ReS dilution Reduce power by inse rt i n g co n tro l ro d s. C Mai n steam line l eak Reduce power by r educing tu rbin e l oad. o Main s t eam lin e l eak Redu ce power b y in sert in g contro l rods. Page 87 01'200 06125/2009 Turkey Point ILC 25 NRC Examination Question 44 KIA 039Al.05 Main and Reheat Steam Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associ a ted with operating the Main and Reheat Steam System controls including:

RCS T-ave

Reference:

This is a classic steam lin e leak. A dilution would cause Tavg to increase.

ADM-200 5.4.3.7 requires for a secondary transient, to reduce power below 100% using steam demand/turbine load. Question history: H.B. Robinson NRC exam given on 6/26/07 question 16 -modified Correct answer: C A Incorrect; Tavg would not go down on dilution event. Plausible; in stem had just diluted. B Incorrect; Tavg would not go down on dilution event. Plausible; in stem had just diluted. C Correct; Tavg decreasing and power increasing indicates steam line leak and per ADM-200 should reduce turbine load. D Incorrect; inserting rods is not in accordance with ADM-200. Plausible; would insert rods for primary transient.

Cognitive level: 2 Have to diagnose event and then determine corrective action Pag e 8 8 0[200

06/25/2009 Turke y Point ILC 25 N R C Examination Question 44 KIA 0 39A I.05 Main a nd Reh ea t Steam Ability to predict and l or monitor changes in parameters (to pr eve nt exceeding de s ign limit s) associated w ith o peratin g the Main a nd Reheat Steam Sys tem contro l s including:

Res T-ave

Reference:

Thi s is a class ic s te a m lin e l ea k. A dilution wou ld cause Tavg to in c rea se. A DM-200 5.4.3.7 require s for a seco nd a r y tran s i en t , t o redu ce power below 100% u s ing stea m demand/turbine l oad. Question hi story: H.B. Robinson N R C exam given on 6/26 1 07 que s tion 16 -modified Correct answer: C A I ncorrect; T avg wo uld 11 0 t go down on dilution event. Plau si ble; in s tem had ju s t diluted. B In correc t; Tavg would not go do w n o n dilution event. Plau s ibl e; in s tem had ju s t diluted . C Co rr ec t; Tav g decreasing a nd p owe r in c rea s ing indicates s team line lea k and per A DM*200 shou ld reduce turbine load. D In correc t; in se rting rod s i s not in accor dan ce w ith ADM*20 0. Plau s ible; would insert rod s for primar y tran s ient. Cog niti ve le ve l: 2 Ha ve t o di a gno se eve n t and then d e temline co rrecti ve act i on Page 88 of 200 Question #45 ES-401 Question 45 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: C Explanation (Optional):

6/25/2009 Form ES-401-5 RO SRO 2 1 039G2.4.45 Alarm C 511 actuates when steam flow greater than feed flow by 500,000 lbslhr on 1/2 channels.

Reactor trip is 112 S/O level at 10% AND 112 steam flow greater than feed flow by 665000 lb/hr. The loss of 3P06 makes up one channel of low level on each S/O. Continuing to reduce feed will cause a reactor trip with the low level already made up. Technical Reference(s):

3-ARP-097.CR p. 15305/08/2009 (Attach if not previously provided) 5610-T -0 sheets 17 & 18B 04/03/2007

& 10/15/2003 (including version/revision number) 5610-T-L1 sheet 11 04/09/2009 Proposed references to be provided to applicants during examination:

None Learning Objective:

6902260 Obi. 6 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 10 55.43 X

Question #45 6 12 512009 ES-401 Written Examination Form ES-401-5 Question Worksheet Question 45 Examination Outline C r oss-Reference

Level RO SRO T ie r # 2 --Group # 1 KIA # 039G2.4.45 Importance Rating ...li.. Proposed Question:

See attached Proposed A nswer: C E x planation (Op tional): A l ann C 511 ac tu ates when steam flow grea t e r t han feed fl ow by 500 , 000 lb slh r on 1 12 c hann e l s. Reactor trip is 1/2 S/G l evel at 10% AND 1/2 s t eam flo w greater than feed flow by 665000 Ib/hr. T h e loss of3P06 makes up o ne c h anne l of l ow l eve l on each S/G. C o ntinuin g to red u ce feed wi ll ca u se a reacto r trip with the lo w level a lr ead y mad e up. Te c hn ic al Reference (s): 3-ARP-097.CR p. 1 5305/08/2009 (A tta c h if not prev io usl y pro v ided) 56 10-T-D shee t s 17 & 18B 04/03/2007

& 10/15/20 03 (i ncluding versio n/re visio n number) 56 10-T-L1 sheet 1104/09/2009 Prop ose d referen c es to be provided to applicants during examination:

N one Learning Objec t ive: 6902260 Obi. 6 (As available)

Question So urce: Bank# M o dified Bank # New __ ,,-(Note c hanges or attach parent) X Question Hi story: La st NRC Exam (Optional: Questions v alida t ed at the facility sinco 10195 will genorolly undergo less rigorous review by the NRC; failure to pro vi de the infolTTlalion will nec e ssitate 8 d e tailed review of evel}' question.)

Question Cognitive Level: 10 C FR Part 55 Content: Comme nt s: Memory or Fundamental Knowledge Compre h ension or Analysis 55.4 1 10 55.43 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 45

Unit 3 was at 100% when 3P06 was lost.

3A S/O increasing slowly.

The BOP is reducing feed to the 3A S/O when the following actuate: Annunciator C 211, SO A NARROW RANOE HI LEVEL Annunciator C 511, SO A STEAM> FEED Bistable status light STM-FW FLOW DEV FC 478 B 1

The reactor is still at 100% power. In accordance with 3-0NOP-003.6 , Loss of 120V Vital Instrument Pane13P06, how should the crew respond to the above event? A The BOP should continue reducing feed flow. A reactor trip will occur if S/O level continues to increase. B The BOP should stop reducing feed flow. A reactor trip will occur if feed flow is reduced further. C The RO should trip the reactor. SI is NOT required.

A reactor trip setpoint has been exceeded. D The RO should trip the reactor and close the MSIVs. A reactor trip setpoint has been exceeded. Page 89 of 200

06/2512009 Turkey Point lL C 25 NRC Examination Question 45

Unit 3 was at 1 00% w hen 3 P06 was l ost.

3A S/G in creasing slow l y.

Th e BOP i s redu c in g f ee d to the 3A S/G whe n the following actuate: A nnun c iator C 2/1 , SG A NA RROW RANGE HI L EVE L Annun c i a t o r C 5/1 , SG A STEAM> FEED Bi s table s tatu s light STM-FW FLOW DEY F C 478 B I

The reactor is st ill at 100% power. I n accordance with 3*0NOP*Q03.6 , Loss of 120V Vital In s trument Panel 3P06, how s h o uld th e c r ew respond to the above eve nt? A T h e BOP s h o uld co ntinue reducing feed flow. A rea cto r trip w ill occur if S/G le ve l continues to i ncrea se. B The BOP s h o uld s t o p redu c ing feed fl ow. A reactor trip wiJI occur if feed flow i s r e du ce d further. C The RO s h o uld trip the reactor. S I is NOT r e quired. A reactor trip sc tp oin t ha s b e en exceeded.

D The RO s hould trip th e r eac tor a nd clo se the MSIVs. A rea c t o r trip se t point h as been exceeded.

Pa ge 8 9 of 2 oo 06125/2009 Turkey Point ILC 25 NRC Examination Question 45 KIA 03902.4.45 Main and Reheat Steam Ability to prioritize and interpret the significance of each annunciator or alarm

Reference:

3-ARP-097.CR p. 153 5610-T-D-17

& 18B 5610-T-Ll sheet 11 Alarm C 5/1 actuates when steam flow greater than feed flow by 500,000 lbslhr on 112 channels.

Reactor trip is 1 1 2 S/O level at 10% AND 112 steam flow greater than feed flow by 665000 Iblhr. Question history: New Correct answer: C A Incorrect; it's correct that a reactor trip will occur ifS/O level continues to increase, but another reactor trip setpoint has been exceeded.

Plausible; reactor trip occurs at 80% S/O level. B Incorrect; reactor trip setpoint already exceeded.

Plausible; need to realize that P06 failure brings in S/O level on each channel. C Correct; S/O level in due to P06 failure and now have 1/2 FF less than SF. D Incorrect; MSIV closure not required.

Plausible; ONOP-003.6 FOP directs closure of MFIVs. Cognitive level: 2 Operator needs to assess situation and determine actions to take. Page 90 of 200

06/25/2009 Turkey P oint ILC 25 NRC Examination Question 45 KIA 039G2.4.45 Main and Reheat Stearn Abi lit y to prioritize and interpret the signi fic ance of each annunciator or alann

Reference:

3-ARP-0 97.CR p. 15 3 5610-T-D-17 & 1 8B 5610-T-L I s he et II Alann C 511 actuates when s team flow greate r than feed flow by 500,000 I bslhr on 1/2 c h annels. Reactor trip is 112 S/G le vel at 10% AND 1 1 2 steam flow greater than feed flow by 665000 Iblhr. Question hi story: New COffee I a n swer: C A I ncorrect; it's correct that a reactor trip w ill occur ifS/G level continues to increase , but another reactor trip selpoi nt has b ee n exceeded.

P l ausible; rea ctor trip occurs at 80% S/G l eve l. B In co rrect; reactor trip s ctpoint already exceeded.

Plausible; need to realize that P06 failure brings in S/G le vel on each c hanneL C Cor re ct; S/G l eve l in due to P0 6 fai l ure a nd now have 112 FF l ess than SF. o In correct; MS I V closure-n ot required, Plausible; ONOP-003.6 FOP directs closure of MFIVs. Cognit i v e l evel: 2 Operator needs to assess situation and determine actions to take . Pag e 90 o f 20 0 Question #46 ES-401 Question 46 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

Lesson 6902111 A section 2.3 & p. 43 RO 2 1 059K3.03 Pressure input failure high causes and increase in indicated steam flow. 6/25/2009 Form ES-401-5 SRO ----The l e v e l e rror signal has an integral and will eventually reduce the total error signal. Technical Reference(s):

__________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902111A Obi. 6 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x Question #46 ES-401 Question 46 Written Examination Question Worksheet E x amination Outline Cross-Reference

Le v el Tier # Group # KIA # Importan ce Rating Proposed Question

See attached Proposed Answer: c E x planation (Optional)

Lesson 6902 111 A sec tion 2.3 & p. 43 RO 2 1 059K3.0 3 Pr essu r e input failure hi g h causes and in c r ease in indi ca t e d s t eam fl ow, 6 12 5 12 009 Form ES-401-5 SRO T h e l eve l error sig nal h as an integra l and will eventua ll y redu ce the t o t a l erro r s i g nal. Technical Reference(s)

,!:5,,6 1!-!Oc-ccT,,-Dc-cc1!..7

-"0,,4/,,0,,3""2"'0"'0,,6

__________

_ (A tta c h if not previously provided).,..

_________________

_ (i ncluding ve rsion/revision number)' ____________________

_ Pr o posed references to be provided to applicants during examination

None Learn i ng Objective: 6902111A Obi. 6 (As available)

Question Source: Bank# Modified Bank # New __ ;:-(Note changes or attach parent) X Question History: Last NRC Exam (Optional: Questions validated at the fac i lity since 10195 will generally undergo less n'gorous rev i ew by rhe NRC: failure to provide Ihe in f oml8lion w ill necessitate a detailed fl3view of every question.)

Question Cognitive Le vel: 10 CFR Part 55 Con tent: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x 06/2512009 Turkey Point ILC 25 NRC Examination Question 46

Unit 3 is at 100% power.

The steam pressure input into the 3A S/G level control system fails high. Which of the following actions will occur? Initially, feedwater flow to the 3A S/G will... A decrease due to lower indicated steam flow. Eventually, the level error signal will reduce the total error signal. B decrease due to lower indicated steam flow. The level error signal will NOT reduce the total error signal. C increase due to higher indicated steam flow. Eventually, the level error signal will reduce the total error signal. D increase due to higher indicated steam flow. The level error signal will NOT reduce the total error signal. Page 91 of 200 06/25/2009 Turkey Point ILC 25 NRC Examination

Question 46

Unit 3 i s at 100% power.

The s team pressure input into the 3A S/G le ve l control system fai l s high. Which oflhe following actions will occur? Initially , feedwater flow to the 3A S/G will ... A decrease due to lower indicated stea m flow. Eventually, the level error s ignal will reduce the total error signal. B decrease due to lower indicated steam flow. The leve l error signal will NOT reduce the tota l error signal. C increase due to higher indi ca ted stea m flow , Eventually, the level error s ignal will reduce the total error signal. D increase due to higher indicated steam flow. The level error s ignal will NOT reduce the total error signal. Page 91 of 200 Question #47 ES-401 Question 47 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: C Explanation (Optional)

6/25/2009 Form ES-401-5 RO SRO 2 1 --061K5.02 ReS pressure is decreasing means adequate cooling. S/G pressure is greater than ReS pressure, so S/Gs are a heat source. Technical Reference( s):

________ _ (Attach if not previously provided)

________________

_ (including version/revision number) ________________

_ Proposed references to be provided to applicants during examination

None Learning Objective:

6902918 Obi. 6 (As available)

Question Source: Bank # Modified Bank # New 1.1.32.18.1.9 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional: Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 x

Q u es ti o n #47 ES-4 01 QUestion 47 Written Examination Question Worksheet Examination Outline Cross*Reference

Level Tier # Group # KIA # Imp orta nce Rating Proposed Question: See attached Proposed Answer: C Explanation (O ptional): 6125/2009 Form E S-401-5 RO SRO 2 1 --061K5.02 2L 2&. ReS p r ess ur e is decreasing m ea ns a dequ ate cooling. S/G pre ss ure is g r ea t e r th a n R eS pressure, so S/Gs are a h ea t so urce. Technical Reference (s): "Le"'sccs"'o"'n."6"S"'O"-29"-1",S"O"'2,, 1.c 1S"'I,, S ________ _ (Attac h if not previously provided):;--___________

____ _ (including ve rsion/revision numbe r) ________________

_ Prop osed references to be provided to applicants during examinatio n: None Le arning Objective:

6902918 Obi-6 (As available)

Questio n Source: Bank # Modified Bank # Ne w 1.1.32.1S.1.9

__ ,,-(Note changes or attach parent) Question Hi story: La st NR C E x am (Optional: Questions valida t ed a t the f acilily since 10195 will generally undergo less rigorous review by the NRC: failure to provide the information wilt necessitate a detailed review o f every question.)

Question Cognit i ve Le vel: 10 C FR Part 55 Coni en!: Comments: Mem ory or F undamental Knowledge Comprehension o r Analysis 55.41 5 5.43 5 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.32.18.1.9 029180109

The unit has experienced a LOCA.

RCS pressure is 800 psig and decreasing.

S/G pressures are 900 psig and steady. How is core cooling being provided?

Core cooling is being provided by: A) the S/Gs and break flow. Core cooling is greater than decay heat product i on. 8) the S/Gs and break flow. Core cooling is less than decay heat production. C) break flow. The S/Gs are NOT providing core cooling. Core cooling is greater than decay heat production. 0) break flow. The S/Gs are NOT providing core cooling. Core cooling is less than decay heat production.

CORRECT or INCORRECT feedback for item: 1.1.32.18.1.9 6900918 RCS press decreasing means adequate cooling. S/G press> RCS press -> S/Gs are heat source Item Classification:

Ana l ysis em difficulty:

0.00 eywords: 009 EK2.03 Item weight: 10 Points required for mastery: 1 Correct alternative(s

): C Judging values of alternatives

A=-1 8=-1 C=1 0=-1 Items in G:\TrnglApps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.32.18.1.9 029180109

The unit has experienced a LOCA.

RCS pressure is 800 pslg and decreasing.

S/G pressures are 900 psig and steady. How is core cooling being provided?

Core coo ling i s being provided by: A) the S/Gs and break flow. Core cooli ng is greater than decay heat production. B) the S/Gs and break flow. Core cooling is less than decay heat production. C) break flow. The S/Gs are NOT providing core cooling. Core coo ling is greater than decay heat production. 0) break flow. The S/Gs are NOT providing core cooling. Core cooling is less than decay heat production. CORRECT or INCORRECT f eedback for item: 1.1.32.18.1.9 6900918 RCS press decreasing means adequate coating. S/G press> RCS press -> S/Gs are heat source Item C la ss ification: Analysis em difficulty:

0.00 eywords: 009 EK2.03 Item weight: 10 Points required for mastery: 1 Correct alternalive(s)

C Judging values of alternatives

A=-1 8=-1 C=1 D=-1 06/25/2009 Turkey Point ILC 25 NRC Examination Question 47 Unit 4 has experienced a small break LOCA.

RCS pressure is 800 psig and decreasing

S/G pressures are 900 psig and steady. How is core cooling being provided and is core cooling more or less than decay heat production?

Core cooling is currently being provided by ... A AFW to the S/Gs and break flow. Core cooling is greater than decay heat production.

B AFW to the S/Gs and break flow. Core cooling is less than decay heat production.

C break flow. AFW to the S/Gs is NOT providing core cooling. Core cooling is greater than decay heat production.

D break flow. AFW to the S/Gs is NOT providing core cooling. Core cooling is less than decay heat production.

Page 93 of 200 06125 1 2009 T u rke y Point IL C 25 N RC Exa mination Question 47 U nit 4 ha s ex p e rien ce d a s mall break LO CA.

ReS pressure i s 800 psig and decreasing

S I G pr essures are 900 p s i g and s tead y. How is core coo l ing being pro v ided and is core coo ling m o r e or les s than decay heat pr o du c tion? Co r e cooling is c urrentl y bein g pro v ided b y ... A AFW to th e S I Gs and break fl ow. Co r e coo lin g i s greater than deca y heat production.

B AFW t o the S I Gs and br eak fl ow. Core coo lin g i s l ess th a n de cay h ea t produ c ti on. C break flow. AFW to the S I Gs is NO T pro v idin g co re coo lin g. Core cooling is greater than decay h ea t production.

D br e ak flow. AFW to th e S I Gs i s NOT pro v iding co re cooling. Co r e coo lin g i s l ess than d ecay he a t produ c tion. Page 9 3 o f 20 0 06/25/2009 Turkey Point ILC 25 NRC Examination Question 47 KIA 061K5.02 Auxiliary/Emergency Feedwater Knowledge of the operational implications of the following concepts as they apply to the Auxiliary/Emergency Feedwater System: Decay heat sources and magnitude

Reference:

LP 6902918 RCS pressure is decreasing means adequate cooling. S/G pressure is greater than ReS pressure, so S/Gs are a heat source. Question history: EXAMINER 1.1.32.18.1.9 Correct answer: C A Incorrect p e r above discussion. Plausible; for many breaks AFW is needed for cooling. B Incorrect per above discussion.

Plausible; for many breaks AFW is needed for cooling. C Correct per above discussion

.. D Incorrect per above discussion.

Plausible; need to realize with RCS pressure decreasing that core cooling is adequate.

Cognitive level: 3 Need to anal y ze stem to determine that AFW is not providing cooling and that core cooling is adequate. P a ge 94 of 200 06/25/2009 Turkey Point lLC 25 NRC Examination Question 47 KJA 061K5.02 Auxiliary/Emergency Feedwater Knowledge of the operational implications of the following concepts as they app l y to the Auxiliary/Emergency Feedwater System: Decay heat sources and magnitude

Reference:

LP 6902918 R eS pressure i s decreasing mean s adequate cooling. S/G pressure is greater than Res pres s ure , so S/Gs are a heat source. Question history: EXAMrNER 1.1.32.18.1.9 Correct answer: C A Incorrect per above discus s ion. P l ausible; for many break s AFW i s needed for cooling. B In co rre ct per above di sc ussion. Plausible; for many break s AFW i s needed for cooling. C Correct per above di sc u ss ion .. o lncorrect per above discus s ion. Plausible; need to realize with ReS pre ss ure decreasing that core coo ling is adequate.

Co gnitive le ve l: 3 Need to analyze stern to detemline that AFW is not providing cooling and that core cooli ng i s adequate.

Pag e 94 or200 Question #48 ES-401 Question 48 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional)

RO 2 1 062K1.02 Technical Reference(s)

3-0NOP-004.3 note before step 1 09/26/2005 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided)

_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902263 Obi 4 (As available)

Question Source: Bank # 1.4.25.63.1.1 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x

Question #48 ES-401 Question 48 Written Examination QUestion Worksheet Examination Outline Cross-Reference

Level Tier# Group # KIA # Importance Rating Proposed Question

See attached Proposed Answer: C Explanation (Optional):

RO _2_ 1 062K1.02 Technical Reference(s)

3-0NOP-004.3 note before step 1 09/26/2005 612s n 009 Form ES-401-5 SRO (Attach if not previously provided),:;-_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902263 Obi 4 (As available)

Quest ion Source: 8ank# Modified Bank # New 1.4.25.63.1.1 ==" (No te changes or attach parent) Question His tory: ' Last NRC E xam (Op t ional: Questions validated at the feci/ity since 1lV95 willgeneral/y undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of eve!}' question.) Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x Items in G:\Trng\Apps\WEXAMINE

\PTN Exam\PTN Exam.xam Item: 1.1.25.63.1.1 9022630101

The unit is at 100% power. All Plant equipment is aligned for normal operations Which of the following symptoms from 3/4-0NOP-004.4 , "Loss of 3/4 C 4KV Sus" indicate a loss of the 3C 4KV bus? A) "A" Main Feedwater Pump B) "C" Reactor Coolant Pump C) "S" Condensate Pump 0) "C" Condensate Pump Item Class i fication: Undefined Item difficulty

0.50 Keywords: NONE Item weight: 1 0 Points required for mastery: 1 Correct alternative(s):

0 Judging values of alternatives

A=-1 B=-1 C=-1 0=1 Memo Field:

REFERENCE:

3/4-0NOP-004.4, Section 2.0 OL: 200 App. RCO, NLO Items in G;\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item; 1.1.25.63.1.1 9022630101

Th e unit is at 100% power. All Plant equipment is aligned for nonnal operations

\Nhich of the following symptoms from 3/4-0NOP-004

.4 , " lo ss o f 3/4 C 4KV Bus" Indicate a loss of the 3C 4KV bus? A) "A" Ma i n Feedwater Pump B) "C" Rea c tor Coolant Pump C) "B" Condensate Pump D) "C" Condensa t e Pump Item C la ssifica tion: Undefined Item difficulty

0.50 Keywords: N O NE Item weigh!: 10 Points required for mastery: 1 Corred alternative(s)

0 Judging values of alternatives

A=-1 B=-l C=-l 0=1 Memo Field:

REFERENCE:

3/4-0NOP-004.4 , Section 2.0 Ol: 200 App. RCO , Nl O

06125/2009 Turkey Point ILC 25 NRC Examination Question 48 Initial conditions

Unit 3 is at 100% power.

Unit 4 is in Mode 3 at normal operating temperature and pressure. Subsequently:

Unit 4 Startup Transformer lockout relay trips and both Unit 4 EDGs fail to start.

Power is restored to the 4B 4kV Bus using the Station Blackout (SBO) Tie.

The Turkey Point switchyard subsequently deenergizes.

The 3A and 3B EDGs start. What is the status of the Unit 3 4kV Buses? 3A 4kY Bus 3B 4kV Bus A Deen e rgized Deenemized B Deenergized Energized C Energi z ed Deenergized D Energized Energized P a ge 95 o f 200 06125/2009 Turkey Point IL C 25 NRC Exam i nat i on

Question 4 8 Initi a l co nditi ons:

Uni t 3 i s at 100% power.

Un it 4 i s in Mode 3 at normal opera tin g temperature a nd pressure.

Subsequently:

Uni t 4 Startup Tr a n sformer l ockout relay trips a nd b o th U nit 4 EDGs fai l t o start.

Power i s restored to th e 48 4kV Bus u sing the Station Blackout (S80) Ti e.

The Turkey P oi nt sw it chyard subsequen tl y deenergizes.

The 3 A and 3 B EDGs s t art. What is the status of th e Unit 3 4kV Buses? 3A 4kV Bus 3 B 4kV Bus A Deenergized Deencmized B Deenergized E n e r g i zed C Ene r g i zed D eene r g i zed

0 E n e r gize d Energized Pag e 95 o f 200 06/2512009 Turkey Point ILC 25 NRC Examination Question 48 KIA 062Kl.02 AC Distribution System Knowledge of the physical connections and/or cause-effect relationships between the AC Electrical Distribution System and the following system: ED/G

Reference:

3-0NOP-004.3 note prior to step 1 -"When 3B 4KV Bus is supplying power to Unit 4 and offsite power to 3B 4KV Bus is lost, 3B Emergency Diesel Generator output breaker will NOT close until the Station Blackout Breaker, 3AD07, has been manually opened." Question history: EXAMINER 1.4.25.63.1.1 Correct answer: C A Incorrect; 3A Bus will be energized via 3A EDG. Plausible; Use of SBO puts electrical in strange configuration and candidate need to know which bus feeds SBO. B Incorrect; 3A Bus will be energized via 3A EDG. Plausible; Use of SBO puts electrical in strange configuration and candidate need to know which bus feeds SBO. C Correct per note in reference.

The 3B EDG will not close onto the 3B 4kV Bus. D Incorrect; 3B Bus will be deenergized.

Plausible; bus stripping does not open SBO. Cognitive level: 2 Need to diagnose for effect of SBO being closed Page 96 of 200 06/25/2009 Turkey Point IL C 25 NRC Examination Question 4 8 KIA 062KI.02 AC Distribution Sys tem Knowledge oflhe physical co nn ections and/o r cause*effect relati o n s hips between the AC Electrical Di s tribution System and the fbllowing system: ED/G

Reference:

3-0NOP-004.3 not e prior to ste p 1 -" When 38 4KV Bus i s supp lying power to Unit 4 and offsite power to 38 4KV Bus i s lo s l , 38 Emergency Diesel Generator output breaker w ill NOT close until the Station Bla c kout Break e r , 3AD07, ha s been manually opened." Que s ti on history: EXAM I NER 1.4.25,63, 1.1 Correct answer: C A I ncorrect; 3 A Bu s w ill be energ i z ed via 3 A EDG. Plausible; U se ofSBO puts electrical in strange configurat ion a nd candidate need to know whic h bus feeds S80. 8 ln correc t; 3A Bu s wi ll be e n erg i zed v ia 3A EDG. Plau s ibl e; U se ofSBO put s ele c tri cal in s trange configuratio n and candidate need to kno w wh i c h bus feeds SBO. C Co rrect per n o t e in reference. The 38 EDG will n o t clo se o nt o th e 3B 4kV Bus. o In correct; 3 B Bu s wi ll be deenergized.

Plausible; bus st ripping doc s n o t ope n sao. Co gniti ve l evel: 2 Need to diagnose for effect o f SBO being closed Pa ge 96 of 200 Question #49 ES-401 Question 49 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

6/2 5/2009 Form ES-401-5 RO SRO 2 --1 063A4.02 The batteries are good for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if non-essential DC loads stripped.

Per the stem, the battery chargers (BC) ultimately powered from the 3A , 4A, & 4B EDGs will be deenergized.

4001: 4B2 BC powered from 3D MCC, remains energized/4B 1 BC powered from 4B MCC de-energized

/One BC to 4DOI will remain energized , meaning 4DOI will remain greater than 105 volts indefinitely (in table> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) 4023: 4AI BC powered from 4C MCC de-energizedl4A2 BC powered from 3D MCC de-energized

/4023 will remain greater than 105 volts for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Technical Reference(s):

T-E-1592 sheets 1/2 12/22/200805/03/2006 (Attach if not previously provided) 4-EOP-ECA-0.0 caution before step 24 10/23/2008 (including version/revision number)BD-EOP-ECA-O

.O caution before step 24 04/05/2009 Proposed references to be provided to applicants during examination:

None Learning Objective: 6902348 Obi-6 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 --X *

Question #49 ES-401 Question 49 Written Examination Question Worksheet E x amination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Prop os ed Question: See attached Proposed Answer: D E x planation (Op tional); RO 2 1 063A4.02 6/25/2009 Form ES-401*5 SRO Th e batlerie s arC good for at l eas t 2 h o ur s if n o n-esse ntial OC l oads s tripp e d. Per th e ste m , th e battery c h a r ge r s (BC) ultimately powered from th e 3 A , 4A , & 4 B E O Gs will be d eene r g i ze d. 4001: 4B2 BC po we r e d from 3 D MCC , r e mains e n erg i zed/4B J Be powe r e d from 48 MeC de-energized

/One BC t o 4001 wi ll remain e ner g i ze d , meaning 4001 w ill r ema in g r ea t er th a n 10 5 vo lt s ind efi nitel y (i n tabl e> 24 h o ur s) 4023: 4A I Be p owered from4C MeC de-energizedl4A2 B C powered from 3 0 MeC de-energized

/4023 w ill remain g r ea ter than 10 5 vo lt s for at l eas t 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s Technical Reference (s): T*E*1592 sheets 1/2 12/22/2008 05/03/2006 (A ttach if not previously provided) 4-EOP-E CA-0.0 caution before step 24 10/2 3/2008 (includ ing version/rev ision number)BD-EOP-ECA-O

.O caution before step 2 4 04/05/2009 Propos e d references to be pro v ided t o applicants during examination

None Learn i ng Objec ti ve: 690 23 48 Obi. 6 (A s available) Question Source: Bank # Modified Bank # New ==cc-(Note changes or attach parent) X Question Hi story: La st NRC EXam (O ptional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC: failure to provide the informatio n will necess i tate a detailed review of every question.)

Question Cognitive L evel: 10 CFR Part 55 Content: Commen t s: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X 06125/2009 Turkey Point ILC 25 NRC Examination Question 49

The PTN switchyard deenergized.

Only the 3B EDG started.

The Unit 4 crew is perfonning 4-EOP-ECA-0.0, Loss of All AC Power.

The Station Blackout Tie will not close. What is the minimum time before the Unit 4 125 VDC busses will be less than 105 Volts as indicated on DCS? 4DOI 4D23 A 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 hours B 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2 hours D greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Page 97 of 200 *

06/25/2009 Turke y P o int lL C 25 NRC E xa min a ti o n Quest i on 49

The PTN sw itchyard deenergized.

Onl y the 3B EDG s tarted.

The U nit 4 crew i s perf o nning 4-EOP-E C A-O.O , Los s of AJI AC Power.

The S tati o n Blackout Tie will n ot clo se. What i s th e minimum time before th e Unit 4 125 V D C bu ss e s will be le ss th an 1 05 Vo lt s as indicated o n D eS? 4DO I 4D2 3 A 2 h ou r s 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s B 2 h ours grea t er than 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s c greater t han 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s 2 h o ur s D greater than 2 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s greate r than 24 h ou r s Page 97 o f 200 0612512009 Turkey Point ILC 25 NRC Examination Question 49 KIA 063A4.02 DC Electrical Distribution Ability to manually operate and/or monitor in the control room: Battery voltage indication

Reference:

4-EOP-ECA-0.0 and BD-EOP-ECA-O.O CAUTION before step 24 states that batteries good for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if non-essential DC loads stripped.

T-E-1592 sheets I & 2 Per the stem, the battery chargers (BC) ultimately powered from the 3A, 4A, & 4B EDGs will be deenergized.

4001:

4B2 BC powered from 3D MCC, remains energized

4Bl BC powered from 4B MCC de-energized

One BC to 4DOl will remain energized , meaning 4DOl will remain greater than 105 volts indefinitely (in table> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) 4D23:

4Al BC powered from 4C MCC de-energized

4A2 BC powered from 3D MCC energized

4023 will remain greater than 105 volts for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Question history: New Correct answer: D A Incorrect; 4DOl BC 4B2 will remain energized.

Plausible; need to realize that 4B2 will remain energized.

B Incorrect; 4001 BC 4B2 will remain energized and 4D23 does not have energized BC. Plausible; need to realize that 4B2 will remain energized and 4D23 doesn't have energized BC C Incorrect; 4D 23 does not have energized BC. Plausible; need to realize 4D23 doesn't have energized BC D Correct per above discussion Cognitive level: 2 Need to reali z e which battery chargers are energized, which DC bus they feed and know how long battery will last if no energized BC. Page 98 of 200 06/25/2009 Turke y Point IL C 25 NRC Exam i nat i o n Question 49 KJ A 063A4.02 DC E l ec tri ca l Distribution Ability to manually operate and/or monitor in the con trol room: Battery vo lta ge indication

Reference:

4-EOP-ECA-O.O a nd BD-EOP-ECA-O.O CAU TIO N before step 24 sta te s that batteries good for at lea s t 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC loads s tripped. T -E-1 592 s he ets I & 2 Per the stem, the battery chargers (Be) ultim ate l y powered fr om the 3A , 4A, & 48 EDGs w ill be deenergized.

4DO I:

482 Be powered from 3D MeC , remains e n erg i zed

481 Be powered from 48 MeC de-energized

One Be to 4D01 w ill remain energized, meaning 4D01 will remain greater than 105 vo lt s indefinitely (in table> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) 4D23:

4A I Be powered from 4C MeC dc-energized

4A2 Be powered from 3D MeC energized

4023 wi ll r emain grea t e r than lOS volts for at l east 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Question hi story: New Cor r ec t a n swer: D A In correct; 4DOI Be 482 will remain ene rgi zed. Plausible; need 1 0 realize that 482 will remain energized.

B I ncorrect; 400 I BC 482 will remain energized and 4023 does not ha ve e n e r g i zed B e. Plausible; ne ed to r ea li ze th at 4B2 w ill r emain energized and 4023 d oesn't ha ve energized BC C In correc t; 40 23 does not hav e energized Be. Plau sib le; ne ed to reali ze 4023 d oes n't have energized Be o Correct per above discussion Cog niti ve level: 2 Need to r ea li z e which battery cha rg e r s are energized , w hich OC bus they feed and know how long battery wi ll l ast i fno energized Be. Page 98 of 2 00 Question #50 ES-401 Question 50 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

RO 2 1 065G2.2.42 6/25 12 009 Form ES-401-5 SRO Lub e oil b e tween 85 and 100 , the EDG can still be considered operable.

Limitations are placed on oper a tion. Below 85 and the EDG is inoperable. System Description

p. 33 -an immersion heater maintains the water in the LO cooler 125-155°F. No upper limit on LO temperature in the P&Ls , but 230° will give an EDG trip if not an emergency start. Technical Reference(s)

4-0P-023 step 4.3301/29/2009 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902136 Obi. 15 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every quest i on.) Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 x * *

Question #5 0 ES-401 Question 50 Written Examination Question Worksheet E x amination Outline Cross-Re fer ence: L evel Tier # G r oup # KIA # Importan ce Rating Proposed Question: See attached Proposed Answer: C Explanation (Optional)

RO 2 1 065G2.2.42 6125/2009 Form ES-401-5 SRO Lube o il between 8S an d 100, the EDG can s till be con sidered operable. Limitations are placed on ope r a ti o n. Below 8S and th e EDG is inoperable.

System Descript i on p. 33 -an immer s ion heat er maintain s the water in the LO cooler 125-1 S5°F. No upper limit on LO t e mperature in th e P&L s , but 230° will give an EDG trip ifnat an eme rgenc y sta rt. Technical Reference(s)

4-0P-023 step 4.33 01/29/2009 (Attach if not previously provided)-,-

_____________

____ _ (including version/revisio n number) ____________________

_ Proposed references to be provided to applicants during examinat i on: None Learning Objective: 6902136 Obi. 15 (As ava i lable) Question Source: Bank# Modified Bank # New __ ::-(Note changes or attach parent) X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC: failure to provide the infonnation will necessitate a detailed review of every question.) Question Cognitive L eve l: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 x 06/25/2009 Turkey Point ILC 25 NRC Examination Question 50 Both units are at 100% power. The ANPO reports the following EDG lube oil temperatures: 4A EDG 160°F 4B EDG 80°F Which one of the following correctly identifies the operability of the Unit 4 EDGs? 4AEDG 4BEDG A OPERABLE OPERABLE B INOPERABLE OPERABLE C OPERABLE INOPERABLE D INOPERABLE INOPERABLE Page 99 of 200 * *

06 1 25 1 2009 Turkey Point ILC 25 NRC Examinat i on Q u e s tion SO Both unit s are at 1 00% power. The AN PO report s the following EOG lube oi l temperature s: >> 4A EDG 160°F >> 4B EDG BO°F Which o n e of the following correctly identifies the operab ilit y of the Unit 4 EDGs? 4AEDG 4B EDG A OPERABLE OPERABLE B I NOPERABLE OPERABLE c OPERABLE INOPERABLE D INO P ERABLE INOPERABLE Pa ge 9 9 o f 2 00 06/25/2009 Turkey Point ILC 25 NRC Examination Question 50 KIA 064G2.2.42 Emergency Diesel Generator Ability to recognize system parameters that are entry-level conditions for Technical Specifications

Reference:

4-0P-023 step 4.33 Lube oil between 85 and 100, the EDG can still be considered operable.

Limitations are placed on operation.

Below 85 and the EDG is inoperable.

System Description

p. 33 -an immersion heater maintains the water in the LO cooler 125-155°F.

No upper limit on LO temperature in the P&Ls, but 230° will give an EDG trip if not an emergency start. Question history: New Correct answer: C A Incorrect per above. Plausible; 100°F puts limits on EDG and 160°F above normal shutdown operations.

B Incorrect per above. Plausible; 100°F puts limits on EDG and 160°F above normal shutdown operations.

C Correct per above reference.

D Incorrect per above. Plausible; 100°F puts limits on EDG and 160°F above normal shutdown operations. Cognitive level: 1 Page 100 of 200

06/25/2009 Turkey P o int IL C 25 NRC Exami nati o n Quest i on 50 KIA 064G2.2.42 E m ergency Diesel Generator Ab ilit y to recognize system parameters th at are entry-l eve l co nditi o n s for Technical Specifications

Reference:

4-0 P-023 step 4.33 Lube o il betwe e n 85 a nd 100, th e EOG can st ill be co n sidered ope r ab l e. L imit ations a r e place d o n operat i on. Be l ow 85 and the EOG i s in ope r ab l e. System Description

p. 33 -an immersion heater maintains the water in th e LO coo l er 12S-J55"F.

No u ppe r limit o n LO temperature in the P&L s , but 230" w ill give a n BOG trip ifn ot a n emergency start. Q u es ti on history: New Co rrect answer: C A In correc t per above. Pl ausible: J OO°F puts limits o n EDG and 160°F above norma l s h u td own operat i ons. B In correct per above. 100°F puts limits on EDG and 1 60 0" F above normal shutdown operat i ons. C Correc t per above reference.

D In correct per above. Plausible; 100°F puts limits on EDG and 160°F above nonnal sh utd own ope r ations. Cogni t ive level: 1 Pag e 10 00[2 00 Question #51 ES-401 Question 51 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

Technical Reference(s)

3-0P-022 section 5.0 01/07/2008 RO 2 1 064K6.08 (Attach if not previously

_________

_ 6/25/2009 Form ES-401-5 SRO (including vers i on/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective:

6902136 Obi. 5.c (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X Que s t ion #5 1 ES-401 QUestion 51 Written Examination Question Workshe e t Examination Outline Cross-

Reference:

Level T ier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: C Explanation (O pt ional): Techn i cal Reference (s): 3-0P-022 sect i on 5.0 01107/200S RO 2 1 06 4 K6.0S 6/2512 00 9 Form ES-401-S SRO (Attach i f not p r eviously provided)-,-T"".",Sc.. "3."'Sc..1c..1"".,,b __________

_ (including ve r si o n/revision number) _________________

__ _ Propo s ed references to be provided to app li cants during exam i nation: N o n e Learning Obje c tive: 6902136 Obi. 5.c (As availab le) Question Source: Bank # Modified Bank # New __ ::-(Note c hanges o r attach parent) X Quest i on History: Last NRC E xa m (Op t ional: Q u estions valid at e d at the f acility since 1 0/9 5 will gene ra ll y un de rg o less rigorous re view by t he NR C: f a i lure 1 0 provide the in f orma t ion w ill necessi t ate 8 de t aile d rev ie w o f e ve ry q ues ti on.) Question Cognitive Level: 10 CFR Part 55 Con t ent: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 51

Unit 3 is at 100% power.

The 3A Emergency Diesel Fuel Oil Transfer Pump is out of service. Which one of the following statements is correct? With local actions , the 3A EDG Fuel Oil Day Tank ... A can be filled by the 3B Emergency Diesel Fuel Oil Transfer Pump. The 3A EDG is OPERABLE in accordance with Tech Specs. B can NOT be filled by the 3B Emergency Diesel Fuel Oil Transfer Pump. The 3A EDG is OPERABLE in accordance with Tech Specs. C can be filled by the 3B Emergency Diesel Fuel Oil Transfer Pump. The 3A EDG is NOT OPERABLE in accordance with Tech Specs. D can NOT be filled by the 3B Emergency Diesel Fuel Oil Transfer Pump. The 3A EDG is NOT OPERABLE in accordance with Tech Specs. Page 101 0[200 06/25/2009 Turk ey P o int IL C 25 N RC Examination Question 5 1

U nit 3 is a t 100% power.

The 3A Emergency Diesel Fuel Oil Transfer Pump i s out of service. Which o n e of th e following s t a t e ment s is correct? With l oca l act ion s, the 3A EOG Fuel Oi l Da y Tank ... A ca n be fill e d b y th e 38 Emergency Di ese l Fu e l Oil Transfer Pump. The 3A EOG is OPERABLE in accordance with Tech S pec s. B can NO T be fill ed b y the 38 Emergency Di ese l Fuel Oil Tran sfe r Pump. The 3A E O G i s OPERABLE in accordance with Tech Specs. C ca n be filled b y the 38 Emerg en cy Die se l Fuel Oi l Transfer Pump. The 3A E OG is NOT OPERABLE in accordance with T ec h Specs. o ca n NO T be filled b y the 3 8 Eme r gency Di ese l Fuel Oil Tran sfe r Pump. Th e 3A E OG i s NOT OPERABLE in accordance with Tech S p ecs .

Pa ge 1010(200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 51 KIA 064K6.0S Emergency Diesel Generator Knowledge of the effect of a loss or malfunction on the following will have on the Emergency Diesel Generators:

Fuel oil storage tanks

Reference:

3-0P-022 section 5.0 T.S. 3.S.1.1.b Question history: New Correct answer: C A Incorrect; the 3A EDG FODT can be filled by the 3B EDG FOTP, but the EDG is not OPERABLE per T.S. Plausible; with FODT capable of being filled, the EDG could be considered OPERABLE.

B Incorrect; the 3A EDG FODT can be filled by the 3B EDG FOTP, but the EDG is not OPERABLE per T.S. Plausible; with FODT capable of being filled, the EDG could be considered OPERABLE.

C Correct; the 3A EDG FODT can be filled by the 3B EDG FOTP and the EDG is not OPERABLE per T.S. D Incorrect:

the 3A EDG FODT can be filled by the 3B EDG FOTP. Plausible; unit separation would prevent this and the EDG is not OPERABLE.

Cognitive level: 1 Page 102 of 200 06/25/2009 Turkey Point IL C 25 NRC Examination Question 51 KIA 064K6.0S Emergency Diesel Generator Knowledge of the effect ofa l oss or malfunction on the following will have on th e Emergen cy Die s el Generat o r s: Fuel o il sto rage tank s

Reference:

3-0P-022 sect ion 5.0 T.S. 3.S.l.l.b Que s ti o n hi s tor y: New Correct answer: C A In co rr ec t; the 3 A EDG FODT can be filled b y the 3B EDG FOTP, but the EDG i s n o t OPERABLE per T.S. Plau s ibl e; with FODT capable o f being fill e d , th e EDG c ould b e considered OPERABLE.

B Incorre ct; the 3A EDG FODT ca n be filled b y the 3B EDG FOTP , but the EDG i s not OPERABLE p er T.S. Plau s ible; w ith FODT capable of being tilled , the EDG could be co n s idered OPERABLE.

C Co rre c t; th e 3A EDG FODT c an b e filled b y the 38 EDG FOTP and the EDG i s not OPERABLE per T.S. D In co rr ec t: the 3A EDG FODT ca n be filled by the 3 8 EDG FOTP. Plau s ibl e; unit se paration would pre ven t thi s and the EDG i s not OPERABLE.

Cognitive le ve l: I Page 102 of200 Question #52 ES-401 Question 52 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional):

Visual observation of display Increased iodine and lOO/Ebar is increased fission fragments.

RO 2 1 073K5.01 Technical Reference(s):

Lesson 6902168 section 2.3.3.7 03/17/08 6/25/2009 Form ES-401*5 SRO --.2JL (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902168 Obi-7 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 x Question #5 2 ES-401 Question 52 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # I mportance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

Visual obse r va tion o f di sp la y Increa se d iodin e and 100/Eba r is increa sed fi ssio n fragments.

RO 2 _1_ 073K5.01 Technical Reference(s):

Lesson 6902168 section 2.3.3.7 03/17108 6/25/2 009 Form ES-401*5 SRO (Attach if not previously provided),::;-

_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902168 Obi. 7 (As available)

Question Source: Bank# Modified Bank # New --c-(Note changes or attach parent) X Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC: failure 1 0 provide the in formati on will necessitate a delailed review of every question.)

Question Cogni t ive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comp rehension or Analysis 55.41 _5_ 55.43 x 06125/2009 Turkey Point ILC 25 NRC Examination Question 52

Chemistry reports an increase in gross equivalent iodine and 100/Ebar activity.

Based on the above report, complete the following. Proces s Radiation Monitor PRMS-3-20, Reactor Coolant Letdown Monitor, will display increased (1) due to increased (2) (1) (2) A cpm Crud B cpm Fission products C mRlhr Crud 0 mRlhr Fission products P a ge 103 of 2 00 06/25/2009 Turk ey P o int IL C 25 N R C E xa min at i o n

Ques ti o n 52

C h e mi s t ry r e p o rts a n in c r ease in gross e qui va l e nt iodine a nd 1 O O/Eb a r ac ti v it y. B ase d o n the a b ove r epo rt , co mpl e te t h e fo ll ow in g. Pr ocess Ra di a ti on M o nit o r Re a ct o r Co ol a nt L e td ow n Mo nitor , w ill di s pl ay in c r eas e d (I) du e to i n c r eased (2) ( I) (2) A c pm C rud B c pm Fi ss i on pr o du c t s C m Rlh r C rud D mRthr Fi ss ion pro d u c t s P a ge 103 or 2 00 06/2512009 Turkey Point ILC 25 NRC Examination Question 52 KIA 073K5.01 Process Radiation Monitoring Knowledge of the operational implications of the following concepts as they apply to the Process Radiation Monitoring System: Radiation theory, including sources, types, units and effects

Reference:

Visual observation of display Increased iodine and 1 OO/Ebar is increased fission fragments.

Question history: New Correct answer: D A Incorrect; display in mRlhr and crud hasn't changed. Plausible; several PRMS channels are cpm and need to realize stem indicates fission products.

B Incorrect; display in mRlhr. Plausible; several PRMS channels are cpm. C Incorrect; crud hasn't changed. Plausible; need to realize stem indicates fission products. D Correct; display is in mRlhr and fission products have increased.

Cognitive level: 2 Need to determine cause of R-20 increase with fuel failure. Page 104 of 200 *

06/25/2009 Turkey Point lL C 2S NRC Examination Question 52 KIA 073K5.01 Process Radiation Monitoring Knowledge of the operational implications of the fol l owing concepts as they app l y to the Pr ocess Radiation Monitoring System: Radiation theory , including so ur ces, type s, units and effects

Reference:

Visual observation of display incre ased iodin e an d IOO/Ebar is increased fission fragments. Question his t ory: New Correct answer: D A In co rre ct; display in mRlhr and crud ha s n't c han ged. Plausible; severa l PRMS c hann e l s are cpm and need to realize stem indicates fission products.

B In correct; display in mRlhr. P l ausib l e; severa l PRMS c hannel s are cpm , C Incorrect; crud hasn't cha n ged, Plau s ible; need t o realiz e stem indicat es fi ssion products. o Co rrect; display is in mR i hr and fi ss ion products have in creased. Cogn iti ve le vel: 2 Need to detcnnine ca u se ofR-20 increase with fuel failure. Pa ge 104 of 200 Question #53 ES-401 Question 53 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: A Explanation (Optional)

Technical Reference(s):

3-ARP-097.CR E 2/205/08/2009 (Attach if not previously provided) 3-0NOP-019 FOP 09/14/2008 RO 2 1 076A2.01 6/25/2009 Form ES-401-5 SRO (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective:

6902277 Obi. 7 (As available)

Question Source: Bank# See comments Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam Class 21 (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 -.-:5=--_

55.43 PTN License exam for class 21 question 77 x * *

Question #5 3 ES-401 QUestion 53 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (O ptional): Technical Reference (s): 3*ARP*097.CR E 212 0510812009 (Attach if not previously provided) 3*0NOP*019 FOP 09/1412008 RO 2 _1_ 076A2.01 6 12 5/2009 Form ES-401*5 SRO (inc luding version/revision number)' ___________________

_ Proposed references t o be provided to applicants during examination:

None Learning Objective: 6902277 Obi. 7 (As available)

Ques t ion Source: Bank # See co mments Modified Bank # __ :;-(Note changes or attach parent) New Question H istory: Last NRC E x am Class 21 (Op t ional: Questions validated at t he facility since 10195 will generally undergo less rigorous roview by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5 __ 55.43 PTN Li cense exa m for c l ass 2 1 questio n 77 x

77. 076A2.01 2 Unit 3 is at 100% power with the '3C' ICW Pump out of service. Annunciator E-2/2 , TURB BEARING HI TEMP , is in alarm. The SNPO reports a massive grass influx has resulted in ICW/CCW and ICWITPCW basket strainer clogging.

The following conditions exist: -Component Cooling Water heat exchanger outlet temperature is currently 118 of and stable. -Turbine bearing temperatures are 181 of and slowly increasing.

-'3A' and '3B' TPCW heat exchangers are at 4200 gpm ICW flow. -'3A', '3B , and '3C' CCW heat exchangers are at 3000 gpm ICW flow each. Which ONE of the following describes the actions that should be taken due to the above conditions?

A. Trip the reactor and turbine and enter EOP-E-O , Reactor Trip or Safety Injection.

B. Reduce turbine load as necessary to return temperatures within nonnal bands and implement ONOP-011 , Screen Wash System/Intake Malfunction.

C. Increase cooling water flow to the turbine lube oil cooler to reduce bearing temperatures and implement ONOP-011 , Screen Wash System/Intake Malfunction.

D. Enter into Technical Specification 3.0.3 and commence a reactor shutdown per GOP-103, Power Operation to Hot Standby. * *

77. 076A2.0 1 2 Unit 3 is at 100% power with the '3C' ICW Pump out of service. Annunciator E-2/2, TURB BEARING HI TEMP , is in alarm. The SNPO reports a massive grass inftux has resulted in ICW/CCW and Icwrrpcw basket strainer clogging. The foltowing conditions exist: -Component Cooling Water heat exchanger outlet temperature is currently 118 OF and stable. -Turbine bearing temperatures are 181 OF and slowly increasing. -'3A' and '3B' TPCW heat exchangers are at 4200 gpm ICW ftow. -'3A', '3B, and '3C' CCW heat exchangers are at 3000 gpm ICW ftow each. Which ONE of the following describes the actions that should be taken due to the above co nditions?

A. Trip the reactor and turbine and enter EOP-E-O, Reactor Trip or Safety Inje c tion. B. Reduce turbine load as necessary to return temperatures within normal bands and implement ONOP-011, Screen Wash System/Intake Malfunction . C. Increase cooling water flow to the turbine lube oil cooler to reduce bearing temperatures and implement ONOP-011 , Screen Wash System/Intake Malfunction. D. Enter into Technical Specification 3.0.3 and commence a reactor shutdown per GOP-103, Power Operation to Hot Standby .

06125/2009 Turkey Point ILC 25 NRC Examination Question 53

Unit 3 is at 100% with the 3C ICW Pump out of service.

A massive grass influx has resulted in ICW/CCW and ICW/TPCW basket strainer clogging.

The following conditions exist: >> CCW Heat Exchanger outlet temperature is currently 118°F and stable. >> Annunciator E 2/2, TURB BEARING HI TEMP, is in alann. >> Turbine bearing temperatures are 181°F and slowly increasing.

>> 3A and 3B TPCW Heat Exchangers are at 4200 gpm ICW flow. >> 3A, 3B, and 3C CCW Heat Exchangers are at 3000 gpm ICW flow each. Which one of the following describes the actions that should be taken in accordance with 3-0NOP-019, Intake Cooling Water Malfunction, due to the above conditions?

A Trip the reactor and turbine and enter 3-EOP-E-0, Reactor Trip or Safety Injection.

B Reduce turbine load as necessary to return temperatures within bands and implement 3-0NOP-Oll, Screen Wash System/Intake Malfunction.

C Increase cooling water flow to the turbine oil cooler and implement 3-0NOP-0 11, Screen Wash System/Intake Malfunction. D Enter into Technical Specifications 3.0.3 and commence a reactor shutdown per 3-0NOP-I00, Fast Load Reduction.

Page 105 of 200

06/25/2009 Turkey P oin t IL C 25 NRC Examination Question 53

U nit 3 is at 100% with the 3C l ew Pump out of service.

A massive grass influ x has resulted in I CW/CCW a nd I CW/TPCW basket strainer clogging.

The following conditions exist: CCW H eat Exc h anger outlet temperature is currently 11 8°F and stable. >> Annunciator E 2/2, TURB BEARING HI TEMP , is in alarm. >> Turb in e bearing t emperatures are 181°F and s l ow l y in c r eas in g, >-3A and 38 TPCW Heat Exchangers are at 4200 b'Pm l ew flow. )i> 3A , 38, and 3C CCW Heat Exchangers are at 3000 gpm leW flow each. Which one of the following describes the actions that should be taken in accordance with 3*0NOP*019, Int ake Cooling Water Malfunc t ion , due to the above cond ition s? A Trip the r cactor and turbine and enter 3-EO P-E-0, Reactor Trip or Safety Injection.

B Reduce turbine l oad as necessary to return temperatures withi n bands and implement 3-0NOP-0II.

Screen Wash System/Intake Malfunction.

C In crease coo lin g water flow to the turbine oil coo l er and implement 3-0NOP-O ll , Sc r een Wash System/Intake Malfunction.

o Enter into Technical Specifications 3.0.3 a nd comme n ce a reactor shutdown per 3-0NOP-100 , Fast Load Reduction . Page lOS o f 2 00 06125/2009 Turkey Point ILC 25 NRC Examination Question 53 KIA 076A2.01 Service Water Ability to (a) predict the impacts of the following malfunctions or operations on the Service Water System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of SWS

Reference:

3-ARP-097.CR E 212 3-0NOP-019 FOP trip criteria Question history: PTN License exam for class 21 question 77 Correct answer: A A Correct; conditions on the turbine bearing are degrading and Annunciator E 212 trip criteria has been met due to bearing temperatures unable to be maintained below 180 0 F. B Incorrect; reactor trip is required.

Plausible; correct action if temperature problem was with the TPCW and maintainable below 180 0 F C Incorrect; reactor trip is required.

Plausible; this is the action to reduce the turbine bearing temperature and should be initiated if the temperature were able to be maintained less than the trip criteria.

D Incorrect, reactor trip is required.

Plausible; correct for total flow of ICW dropping below minimum flow rate of 12,400 gpm for more than 5 minutes. Cognitive level: 2 Need to diagnose situation and apply actions in ONOP-O 19 Page 106 of 200 06/25/2009 Turk ey P oint IL C 25 N R C Exam inati o n Question 53 KJ A 076A2.0 I Serv i ce Wat e r Abi lit y t o (a) predict the impacts of the following ma l functions or ope ration s on th e Service Water Syste m; and (b) b ase d on tho se predictions , u se p roced ur es to correc t , co ntr o l , or mitigate the conseque n ces orl h ase malfunc tions or opera ti ons: Loss o f SWS R efere n ce: 3-ARP-097.CR E 2/2 3-0NOP-0 19 FOP trip cri teri a Question hi sto r y: PTN License exa m for cl ass 2 1 question 77 Correct answer: A A Co rr ec t; cond iti ons on the turbine bearing a rc d egra din g and Annunciator E 2/2 trip criteria h as been met due to bearing t e mperatur es unabl e to be maint a ined b e l ow 1 80 o F. B In correct; reactor trip is requir ed. Plausib l e; co rrc c t action if temperature prob l em was wit h th e TPCW a nd maintainable below 1 80 0 F

C In co rr ect; reactor trip i s requ ired. Plau s ible; this i s the action t o r e du ce the turbin e bearing tempe r ature and s h o uld be initiated if the temperature were able to be m ain t ai n ed le ss than the trip c riteri a. o In co rr ect, rea c t o r trip is r e quir ed. P l ausib l e; co rr ec t for t ota l fl ow of l ew dropping below minimum fl ow rate of 1 2,400 gpm f or m ore than 5 minut es. Cogn iti ve level: 2 Need to diagnose s itu a ti on and a ppl y act i o n s in ONOP-019 Pa ge 1060[200 Question #54 ES-401 Question 54 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: D Explanation (Optional)

RO 2 1 078K2.02 3CM breaker is 34104 -3E LC. Service air compressors are on LC 3E & 3G All of these LCs are de-energized on LOOP. Technical Reference(s):

3-0P-013 Att. 4 03/21/2009

p. 2 of 2 (Attach if not previously provided) 0-NOP-013.1 Att 2 p. 2 of 2 03/25/2009 6/25/2009 Form ES-401*5 SRO (including versionlrevision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902179 Obi. 4/6902145 Obi. 5 (As available)

Question Source: Bank# Modified Bank # New ___ (Note changes or attach parent) X Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X *

Question #54 ES-401 Question 54 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: o E x planation (Op tional): RO 2 _1_ 078K2.02 3CM breaker is 34 104 -3E Le. Se r v i ce a ir compressors are on LC 3E & 3G A ll of the se LCs are de-energi z ed o n LOOP. Technical Reference (s): 3-0P-013 Art. 4 03/21/2009

p. 2 of 2 (Att ach if n o t previously provided) 0-NOP-013.1 Att 2 P. 2 of 2 03/25/2009 6/25/2 009 Form ES-401-5 SRO --....M... (including version/r evisio n number) ___________________

_ Proposed r eferences to be provided to applicants during e x amination: None Learning Objective:

6902179 Obi. 4/69 02145 Obi. 5 (As available) Question Source: Bank # Modified Bank # New __ ,,-(Note changes or attach parent) X Question History: Last NRC Exam (Optional: Questions validaled at the facility since 10195 will generally undergo less rigorous review by the NRC: failure to provide the illfonnation will necessitate a detailed review o f every question.)

Question Cognitive L evel: 10 CFR Part 55 Con ten t: Comments: Memory or Fundamental Knowledge Comprehensio n or Ana l ysis 55.41 _7_ 55.43 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 54

PTN has experienced a dual-unit loss of off-site power.

The 3B EDG did not start. What is the availability of the following air compressors?

A 3CM, Unit 3 Instrument Air Motor Compressor, is available OCM1, Service Air Compressor, is available B 3CM, Unit 3 Instrument Air Motor Compressor, is available OCM1, Service Air Compressor, is NOT available C 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCM1, Service Air Compressor, is available D 3CM , Unit 3 Instrument Air Motor Compressor, is NOT available OCM 1, Service Air Compressor, is NOT available Page 107 of 200

06/25/2009 Turkey Point ILC 25 NRC Examinatio n Question 54

PT N h as experienced a dual-unit loss of off-site power.

The 38 EDG did not start. What is the availability oflhe following air compressors?

A 3CM, Unit 3 In strument Air Motor Compressor, is available OeM I , Serv i ce Air Compressor, is availab le B 3CM , Unit 3 in st nlm ent Air Motor Compressor , is available OeM I , Service Air Compressor , is NOT available C 3CM, Unit 3 In s trum ent A ir Motor Compressor, is NOT available oeM 1 , Service Air Compressor , is avai labl e o 3CM, Unit 3 In strument Air Motor Compressor, is NOT available OeM 1, Service Air Compressor, is NOT avai l ab le Pag e 107 of200 Question 54 KIA 078K2.02 Instrument Air 06/2512009 Turkey Point ILC 25 NRC Examination Knowledge of bus power supplies to the following:

Emergency air compressor

Reference:

3-0P-013 Attachment 4 p. 2 of2 -3CM breaker is 34104 -3E LC 0-NOP-0l3.0l Attachment 2 p. 2 of2 -the service air compressors are on LC 3E & 3G All of these LCs are de-energized on LOOP. Question history: New Correct answer: D A Incorrect; neither is available.

Plausible; need to know power supplies and what is energized on LOOP. B Incorrect; 3CM is not available.

Plausible; need to know power supplies and what is energized on LOOP. C Incorrect; OCM 112 are not available.

Plausible; need to know power supplies and what is energized on LOOP. o Correct; neither is available Cognitive level: 1 Need to compare power supplies to what is energized on LOOP. Page 108 of 200 Ques ti on 54 KIA 078K2.02 Instrument Air 06/2512009 Turkey Point lL C 25 NRC Exam i nation Knowledge of bus power supplies to the following:

Emergency air compresso r

Reference:

3-0P-013 Attachme nt 4 p. 2 of2 -3CM breaker is 34104 -3E LC O-NOP-OJ3.01 Attachment 2 p. 2 of2 -the service air compressors are o n LC 3E & 3G Al l of these Le s a r e de-energized on LOOP. Question history; New Correct answer: D A In correc t; neither is avai l ab l e. Plau s ibl e; n eed to know power supp li es and what is e n ergized on LOOP. B In correct; 3CM i s n OI availab l e. Plausible; need to know power s upplies and wha t is energized on LOOP. C Incorrect; OeM 1/2 are not avai l able. Plausible; need to know power su pplies and what is energized on LOOP. D Correct; neither is avai l able Cogn i tive l eve l: I Need to compare power supp li es to what is energized on LOOP. Page lOS of 200 Question #55 ES-401 Written Examination Question Worksheet Question 55 Examination Outline Cross-Reference

Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

Minimum pressure is negative 2.0 psig. Maximum temperature is 120°F. Level Tier# Group # KIA # Importance Rating RO 2 1 103A1.01 6/25/2009 Form ES-401*5 SRO Technical Reference(s)

. ...:..1

_____________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902126 Obi 9.e (As available)

Question Source: Bank# Modified Bank # New 1.1.28.26.1.3 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional: Questions validated at t he facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed rev i ew of every question.) Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 x *

Que s tion #55 ES-401 Written Examination Question Worksheet Question 55 Examination Outline Cross-Ref erence: Proposed Question:

See attached Proposed Answe r: C Explanation (Op tional): Minimum pres s ure i s negati v e 2.0 psig. Maximum t emperat ure i s 120°F. Le vel Tier # Group # KIA # Importan ce Rating RO 2 _1_ 1 03A l.0l 6/2 5 12 00 9 Form ES-401-5 SRO Technical Reference (s): "'3"-'.6"-.1L*,,41"'5

'-____________

_ (A ttach if not previously provided)-,-_________________

_ (including version/revision numbe r) ____________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902126 Obi 9.e (As avaitable)

Question Source: Bank # Modified Bank # New 1.1.28.26.1.3 __ ,,-(Note changes or attach parent) Question History: La st NRC E xa m (Optional: Que s tions validated at the fecility s i nce 10195 will generally undergo less rigorous rev i ew by (h e NRC; failure to provide the in f ormation will necessitate a deteiled review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.28.26.1.3

"'9025260103;

Unit 3 is in Mode 1

Initially, Containment temperature was 12rF

Containment temperature has been reduced to 118°F

Containment pressure is now a negative 2.2 psig Which of the following is required by Tech Specs? (Disregard the equivalent hours specification for temperature

.) A) Containment temperature should be reduced. Containment pressure is OK at present value. 8) Containment pressure should be increased.

Containment temperature is OK at present value. C) Containment temperature and pressure are OK at present values. 0) Containment temperature should be reduced. Containment pressure should be increased. Item Classification

Knowledge Item difficulty

0.50 Keywords: LOP. 103 A 1.01 , RCa Audit Exam Item weight: 10 " oints required for mastery: 1 orrect alternative(s):

8 Judging values of alternatives

A=-1 8=1 C=-1 0=-1 Memo Field:

Reference:

Tech Spec 3.6.1.4/5 SRO-20 Pre-License Audit Exam #2 Items in G:\Trng\Apps\WEXAMt NE\PTN Exam\PTN Exam.xam Ilem: 1.1.28.26 , 1.3 9025260 1 03;

Unit 3 is in Mode 1

Initially , Containment temperature was 1 2rF

Containment temperature has been reduced to 118°F

Containment pressure is now a negative 2.2 psig VVhich of the following is required by Te ch Specs? (Di srega rd the equivalent hours specification for temperature

.) A) Containment temperature should be reduced. Containment pressure is OK al present value , B) Containment pressure should be increased.

Containmen t temperature is OK at present value. C) Containment temperature and pressure are OK at present values. D) Containment temperature should be reduced. Containment pressure should be increased. lIem Knowledge lIem difficulty

0.50 Keywords: LOP. 103 A 1.01 , RCO Audit Exam Item weight 10 required for mastery: 1 alternative(s)

B Judging values of alternatives

A=*1 8=1 C=-1 D=-1 Memo Field:

Reference:

Tech Spec 3.B.1A/S SRO*20 Pre-License Audit Exam #2

06/25/2009 Turkey Point ILC 25 NRC Examination Question 55

Unit 3 is in Mode 1.

Containment temperature is 118°F.

Containment pressure is a negative 2.2 psig. Which one of the following is required to meet Technical Specifications LCO? A Containment temperature should be reduced. Containment pressure should be increased.

B Containment temperature should be reduced. Containment pressure is within limits at the present value. C Containment temperature is within limits at the present value. Containment pressure should be increased. D Containment temperature is within limits at the present value Containment pressure is within limits at the present value. Page 109 of 200

06/25/2009 T ur key P o int IL C 25 NRC Exam in a t ion Question 55

Un it 3 i s in Mode I.

Co nt ainment temp e rature i s 11 8°F.

Co ntainment pre ss ure i s a neg a tive 2.2 p s i g. Which o ne of the foll ow ing i s requ ir ed t o meet Tech ni ca l S pe cifica ti ons LeO? A Co ntainment t e mperature s h o uld he reduced. Co ntainment pre ssu re sho uld be i nc r eased. 8 Co nt a inm e nt tempera ture s hould he redu ced. Co ntainment pres s ure i s with in limit s at the pr esent v alue. C C ontainment t empera tur e i s with in limit s at the pre se nt va lu e. Co ntainment pr ess ure s hould be in c r eased. o Co nt a inm e nt temp erature i s with in limit s at the pre se nt va lue Co nt ai nm ent pre ss ure i s wi thin li mit s at the pre se nt v alue. P age 1 09 of200 06/2512009 Turkey Point ILC 25 NRC Examination Question 55 KIA 103Al.Ol Containment Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Containment System controls including:

Containment pressure, temperature and humidity

Reference:

Tech Specs 3.6.1.4/5 Minimum pressure is negative 2.0 psig. Maximum temperature is 120°F. Question history: EXAMINER 1.1.28.26.1.3 Correct answer: C A Incorrect; temperature does not need to be reduced. Plausible; near the limit of 120°F. B Incorrect; temperature does not need to be reduced and pressure needs to be increased.

Plausible; near the limit of 120°F and 2.0 psig. C Correct per above reference o Incorrect; pressure needs to be increased.

Plausible; near the limit of2.0 psig. Cognitive level: 1 Page 1100[200

06125/2009 Turk ey P oin t IL C 2S NRC Q u estion S5 KIA 1 03A I.0 1 Containment Abili t y to predic t and/or monitor changes in parameter s (to p r event exceedi n g des i gn limi ts) assoc i ated w i th ope r ating the Containme nt System contro l s including:

Co ntainment p r essure, t empe r ature and humidit y Refer e n ce: Tech S p ecs 3.6.1.4/5 Mi nim um pre ss ure i s ne gative 2.0 p s i g. Maximum temperatur e is 1 20°F. Question hi s tor y: EXAM I NER 1.1.2 8.26.1.3 C orrect answer: C A In correct; temperature does not need to be r e du ce d. Plau s ible; n ear the limit of 1 20°F. B In correc t; temperature d oes not need to be reduced an d pre ss ur e needs to be increased. Pl ausib l e; near t h e l imit of 1 20°F and 2.0 p s ig. C Co rrect per above reference o I ncorrec t; pre ss ure need s to he i ncreased.

Pl ausible; ne a r the limit of2.0 p s i g. Cogni ti ve l evel: I Page 1 10 o f 200 Question #56 ES-401 Question 56 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: B Explanation (Optional):

6/25/2009 Form ES-401*5 RO SRO 2 --2 011K6.06 Hey 121 is normally fully open. The demand for fully open is O. To increase flow through the labyrinth seals, Hey 121 must be throttled in the closed direction. This means demand will be increased above O. The charging pumps are positive displacement pumps and demand is not changed by throttling Hey 121; therefore flow is not changed. Technical Reference(s):

4-ARP-097.CR A 6/5 & G 1/1 03/20/2009 (Attach if not previously provided) 5614-M-3047 sheet 2 07/31/2007 (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902113 Obi. 5j & 6 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X

Question #56 ES401 Qu es ti on 5 6 Writt e n Examination Question Worksheet EXamination Outline Cross-

Reference:

L evel T ier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answe r: B Exp l analion (Op lional): 612512009 Form E S401-S RO SRO 2 --2 --011K6.06 H CV-4-1 21 i s n o rm a ll y flllly open. Th e demand for fully open is O. To increase flow throu g h th e labyrinth sea l s. H C V-4-1 2 1 mu st be thr ott l ed in the c l osed direction.

Th i s m ea n s demand w ill be increased above O. The charging pumps a r c positive d i splace ment pumps and demand i s not c h a n ge d by throttlin g H CV-4-121; therefore flo w i s n o t c h a n ged . Technical Reference(s

): 4-AR P-097.CR A 6/5 & G 1/1 03/20/2009 (A ttach if not previous l y provided) 5614-M-3047 sheet 2 07/3 1/2007 (i nclud i ng version/revision number) ___________________

_ Proposed references to be provided to applicants duri ng e x aminatio n: No n e Learning Objective: 6902113 Obi. 5i & 6 (As avai l able) Question Source: Bank# Modified Bank # New --7"" (Note changes or attach parent) X Question History: L ast NRC E x a m (Optional: Ques t ions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate 8 detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Conlent Comments: Memory or Fundamental K n owledge Comp r ehension or Analysis 55.41 _7_ 55.43 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 56

Unit 4 is at 40% power with Pressurizer level above program.

The following alarms have actuated: A 6/5 RCP LABYRINTH SEAL LO G Ill , CHARGING PUMP LO SPEED How should HCV-4-121 , be adjusted to increase the RCP Labyrinth seal and how will this effect the charging pump flow rate? A Increase HCV-4-121 demand from 0%. Total flow through the charging pump will decrease.

B Increase HCV 121 demand from 0%. Total flow through the charging pump will NOT change. C Decrease HCV-4-121 demand from 100%. Total flow through the charging pump will decrease.

D Decrease HCV-4-121 demand from 100%. Total flow through the charging pump will NOT change. Page 111 of200 *

06/25/2009 Turke y Point ILC 25 NRC Examinat i on Question 5 6

Unit 4 i s at 40% power w i th Pr ess uri zer l ev el above program.

The f O ll ow ing a l anns ha ve actuated:

>> A 6/5 R C P LABYRfNTH SEAL LO 6P >> G I II , C HAR GfNG PUMP LO S PEED H ow s h o uld H CV-4-1 2 1 , be adjus t ed t o in c r ease t h e R e p Labyrinth sea l fl.p a nd h ow wi ll thi s effect the c har ging pump fl ow rate? A In c r ease H CV-4-121 d e m a nd from 0%. To t a l flow th r o ugh the cha r g i ng pump will de crease. B In crease H CY-4-121 dema nd fr om 0%. To t al flow thr o u gh the c h a r g in g pump wi ll N OT c han ge. C De c r ease H CV-4-121 demand from \00%. Tota l flow through the c h a rgin g pump w ill de c reas e. o Decr ease H CY-4-121 dema nd from 1 00%. T o t a l fl ow through the charg in g pump w ill NOT c h a nge . P age III of200 06/2512009 Turkey Point ILC 25 NRC Examination Question 56 KJA 011K6.06 Pressurizer Level Control Knowledge of the effect of a loss or malfunction on the following will have on Pressurizer Level Control: Correlation of demand signal indication on charging pump flow valve controller to the valve position

Reference:

4-ARP-097.CR pp. 55 & 345 5614-M-3047 sheet 2 HCY-4-121 is normally fully open. The demand for fully open is O. To increase flow through the labyrinth seals, HCY 121 must be throttled in the closed direction.

This means demand will be increased above O. The charging pumps are positive displacement pumps and demand is not changed by throttling HCY 121; therefore, flow is not changed. Question history: New Correct answer: B A Incorrect; total flow will not change. Plausible; flow through HCY 121 will decrease.

B Correct; need to increase demand from 0% and flow will not change. C Incorrect; need to increase from 0% and total flow will not change. Plausible; HCY 121 is fully open and flow through HCY-4-121 will decrease.

o Incorrect; total flow will not change. Plausible; flow through HCY 121 will decrease.

Cognitive level: 2 Need to realize that demand for HCY-4-121 fully open is 0, so must increase demand and that charging pumps are posi tive displacement and H CY 121 changing does not change charging pump demand. Page 1120[200

06/25/2 00 9 Turk ey Point IL C 25 NRC Exa mination Question 56 KIA 0 11K 6.06 Pressurizer L evel Contro l Kn ow l edge of the effec t of a l oss o r malfun ct i o n o n th e f o ll ow ing w ill h ave o n Pressuriz e r Level Contro l: Corre l a tion of d e m a nd signa l indication o n charging pump fl ow va l ve contro ller t o the va l ve position

Reference:

4-ARP-097.CR pp. 55 & 345 56 14-M-3047 shee t 2 H CV-4-1 2 1 is n o n na ll y fully o p e n. Th e d ema nd f o r fully o p en i s O. To in c r ease fl ow thr o u g h th e lab yr inth seals, H ey 121 must be throttled in th e closed direction.

This me a n s dem a nd wi ll be in c r eased a b ove O. The cha r gi n g pumps a re positive di s placement pump s and d emand i s n o t cha n ge d by thr ott l in g H eV 1 2 1; th e ref o r e , fl ow is n o t c han ged. Que s tion hi s tory: New Correct answer: B A In correct; t ota l flow w ill n ot c h a n ge. Plau s ible; fl ow thr ough H CV-4-1 2 1 will decrease. B Co rr ec t; n eed to in c re ase demand from 0% a nd flow will not c h ange. C I ncorre c t; need to in c rea se from 0% and total flow will not c han ge. Pl a u s ible; HCV-4-121 i s fully open an d fl ow through H CV-4-12 1 will decrease.

D In co rr ec t; total fl ow w ill not c han ge. Plausible; flow thr ough Hey 1 2 1 w ill decrease.

Cogni ti v e l evel: 2 Need t o re a li ze that demand for HCV-4-121 f ull y open is 0 , so mu s t in crease d e m a nd and th a t c h argi n g pump s a r e positive displacement a nd HCV-4-12 1 c h anging d oes n o t change c ha rg in g pump demand. Pa ge 11 2 of200 Question #57 ES-401 Question 57 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional)

Technical Reference(s)

0-ADM-209 step 4.603/11/2009 6/25/2009 Form ES-401-5 RO SRO 2 2 --016G2.4.3 ...l.L (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learn i ng Objective:

6902008 Obi 1.e (As available)

Question Source: Bank# Modified Bank # New 1.1.24.28.2.6 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _6_ 55.43 x Que s tion #5 7 ES-401 Qu e st io n 57 Wr i tten E xa m i n a t io n Qu es tion Wo r ksh ee t Examination Outline C r oss-Reference

L evel Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: B Explanalion (Optional)

Technical Re f erence(s):

0-ADM-209 step 4.603/1112009 RO 2 2 016G2.4.3 6125 12 009 Fo r m ES-401-5 SRO (Attach i f not previo u s ly p r ovided)-,-

_________________

_ (including version/revision number)' ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902008 Obj 1.e (As available)

Question Source: Bank # Modified Bank # New 1.1.24.28.2.6 _---, ,,.-(N ote changes or attach pa r ent) Question H istory: Last NRC Exam (Op tion al: Questions valida ted at the facility since 10/95 will generally undergo less rigorous reView by the NRC; failure t o provide the in formation will necessi tat e a detailed review o f every queslion.)

Question Cognitive L evel: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comp r ehension or Ana l ysis 55.41 _6_ 55.43 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.28.2.6 9021280206 How is Control Room instrumentation identified that may be relied upon in a post-accident situation?

A) Red vinyl tape 8) Purple vinyl tape C) Red with white letters 0) Yellow with black letters CORRECT or INCORRECT feedback for item: 1.1.24.28.2.6 ADM 2094.6 Item Classification

Knowledge Item difficulty

0.00 Keywords: 2.4.3 Item weight: 10 Points required for mastery: 1 Correct alternative(s)

8 Judging values of alternatives

A=-1 8=1 C=-1 0=-1 Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.2 4.28.2.6 9021280206 ow is Control Room instrumentation iden t ified that may be relied upon in a post-accident situation?

A) Red vinyl tape 8) Purple vinyl tape C) Red w ith while letters D) Yellow with black letters CORRECT or INCORRECT feedback f o r item: 1.1.24.28.2.6 A DM 209 4.6 Item Classificalion:

Knowledge Item difficulty

0.00 Keywords: 2.4.3 It em weight: 10 Points required for mastery: 1 Correc t alternative(s):

8 Judging values of alte rnotiv es: A=-1 8=1 C=-l 0::-1

06/25/2009 Turkey Point ILC 25 NRC Examination Question 57 In accordance with 0-ADM-209, Equipment Tagging and Labeling, how can accident instrumentation be identified?

A Red vinyl tape B Purple vinyl tape C Red placard with white letters D Yellow placard with black letters Page 113 of 200 *

06/25/2009 Turkey Point I LC 25 NRC Examination Question 57 I n accordance with O-ADM-209 , Equipment Tagging and Labeling, how can po saccident instrumentation be identified?

A Red v iny l tape B Purple viny l tape C Red placard with white l etters o Yellow placard with black letters Page 113 of200 06/2512009 Turkey Point ILC 25 NRC Examination Question 57 KIA 016G2.4.3 Non-nuclear instrumentation Ability to identify post-accident instrumentation

Reference:

O-ADM 209 step 4.6 Question history: EXAMfNER 1.1.24.28.2.6 Correct answer: B A Incorrect; wrong color. Plausible; vinyl tape B Correct lAW 0-ADM-209 C Incorrect; not in agreement with ADM-209. Plausible; per ADM-209 Enclosure 3 this is the requirement for permanent danger tags. D Incorrect; not in agreement with ADM-209. Plausible; per ADM-209 Enclosure 3 this is the requirement for alternate shutdown components.

Cognitive level: 1 Page 1140[200 06/25/2009 Turkey P o int lLC 25 N R C Examination Qllcstion 57 KJA 01602.4.3 No n-nuclear instrumentation Ability to identi fy instrumentation

Reference:

O-ADM 209 step 4.6 Question hi story: EXAMINER 1.1.24.28.2.6 Correct answer: B A In correc t; wrong co l or. Plausible; viny l tape B Correct l AW 0-ADM-209 C In correc t; not in agreemen t with ADM-209. Plausible; per ADM-209 Enclosure 3 this i s the requirement for pcnnanenl danger tags. D In co rre ct; not in agreement with ADM-209. Plau s ible; per ADM-209 Enclosure 3 thi s i s the requirement for alternate shutdown compone nt s. Cog niti ve level: 1 Page 114 o f 2 0 0 Question #58 ES-401 Question 58 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: C Explanation (Optional):

Technical Reference(s)

3-NOP-053 step 2.1.4 12/19/2008 RO 2 2 029A2.03 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902129 Obi-9.a (As available)

Question Source: Bank# 1.1.24.39.3.1 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 x Ques t i o n #58 ES-401 Q ues t i on 58 Wr i tten E x aminat i on Q ues tion Wo rk sheet Examination Outline Cross-

Reference:

Level Tier# Group # KiA # I mportance Rating Proposed Questio n: See attached Proposed Answer: C Explana t ion (O ptional): T echnical Reference(s)

3-NOP-053 step 2.1.4 12/19/2008 6/25/2009 F o r m ES-4 01-5 RO SRO _2_ --2 029A2.03 ...rL ..1J... (Attach if not p r eviously provided):;-

_________________

_ (including version/revision number) ____________________

_ Proposed references to be p r ovided to applicants during examination

None Learning Objective: 6902129 Obi. 9.a (As available)

Question Source: Bank # Modified Bank # New 1.1.24.39.3.1

==:;-(N ote changes or attach pa r e n t) Question History: Last NRC Exam (Optional: Questions valfdated at the facility since 10/95 will generally undergo less n'gorous review by th e NRO; f ailure to provide the information will necessitate a detailed review o f every question.)

Ques t ion Cognitive L evel: 10 CFR Part 55 Content: Comments: Memory o r Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 x Items i n G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.39.3.1 9021390301

Each of the station batteries is sized to carry its expected shutdown loads following a plant trip and loss of all AC power fc a period of: A) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 8) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 0) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Item Classification

Knowledge Item difficulty:

0.50 Keywords:

LOP, NPO, STA , 063 A1.01 , NSO Item weight: 10 Points required for mastery: 1 Correct alternative(s)

8 Judging values of alternatives:

A=-1 8=1 C=-1 0=-1 Memo Field:

REFERENCE:

SO-144 Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.39.3.1 Each of the statio n batteries is sized to carry its expected s h utdown loads following a plant trip and l oss of all AC powe r f( a period of: A) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 8) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C) 4 h ours 0) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Item C l assification:

Knowledge Item difficulty

0.50 Keywords: LOP , NPO, STA, 063 A1.01, NSO Item weight: 10 Points required for mastery: 1 Correct alternative(s):

8 Judging values of alternatives:

A=-1 8=1 C=-l 0=-1 Memo Field:

REFERENCE:

SD-144 06/25/2009 Turkey Point ILC 25 NRC Examination Question 58 Initial conditions:

Unit 3 was at 100% power.

A Containment purge has been initiated in accordance with 3-NOP-053, Containment Purge System.

The following fans are started: 4V20, Unit 4 Containment Purge Exhaust Fan 3V9, Unit 3 Containment Purge Supply Fan Subsequently:

PRMS-R-3-11, Particulate Radiation Monitor , alarms. In accordance with 3-NOP-053, what is the effect of the R-ll alarm? A Both fans will trip. Containment isolation is achieved only if the dampers close. B Both fans will trip. Containment isolation is achieved even if the dampers fail to close. COnly 3V9 will trip. Containment isolation is achieved by the purge dampers. 4 V20 is stopped to prevent damage to the fan. D Only 3V9 will trip. 4V20 must be stopped to achieve Containment isolation.

Pagel150f200

06/2 5/20 0 9 Turk ey P o int IL C 25 N R C Exa min a ti o n Qu es ti o n 58 Initi a l co ndit io n s:

U n i t 3 w as a t 10 0% p owe r.

A Co nt a inm e n t pu rge h as b ee n in i t ia t ed in ac cord a n ce w ith 3-N OP-0 5 3, Co nt a inm e nt Pur ge Sys t e m.

Th e f o ll ow in g fa ns a r e sta rt e d: }> 4 V20, U nit 4 Co nt a inm e nt Pur ge E xh a u st F a n }> 3V9 , U n i t 3 Co nt a inm e nt Pur ge S uppl y Fa n S ub seq u e ntl y:

PRM S-R-3-ll , P a rti c ul a t e R ad i a t io n M onit or , a l a rm s. I n acco r da n ce w ith 3-NO P-OSJ, w h at i s the e f fec t of th e R-I l a l arm? A Bo th f a n s w ill trip. Co nt a inm e n t i so l a ti on i s ac hi ev ed o nl y if th e da m pers close. B B o th f a n s w ill trip. Co nt ai nm e nt i so l a ti on i s ac hi ev ed eve n if th e da mp e r s fa il t o cl ose. CO nl y 3V9 wi ll trip. Co nt ai nm e nt iso l a ti on i s ac hi ev e d b y the p ur ge d a mp e r s. 4 V20 i s s t opped t o pr eve nt d a ma ge t o th e fan. o O nl y 3V9 w ill trip. 4V2 0 mu st b e s t o pp e d to ac hi eve Co ntaimn e nt i so lati o n. Page 1 15 o r200 Question 58 KJ A 029A2.03 Containment Purge 0612512009 Turkey Point ILC 25 NRC Examination Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Startup operations and the associated required valve lineups

Reference:

3-NOP-053 step 2.1.4 Question history: EXAMINER 1.1.24.39.3.1 Correct answer: C A Incorrect; only 3V9 will trip. Plausible; expect CVI signal to isolate Containment.

B Incorrect; only 3V9 will trip. Plausible; expect CVI signal to isolate Containment.

C Correct; only 3V9 trips and Containment isolated.

4V20 stopped to protect fan. D Incorrect; 4V20 stopped to protect fan. Plausible; stopping purge exhaust fan part of CVI. Cognitive level: 1 Page 1160[200

Q ue s ti on 58 KJA 029A2.03 Co nt a inm ent Pur ge 0612512009 Turk ey Point IL C 25 N RC Examination Abi lit y to (a) predict the impa c t s of t h e following malfun c ti o n s or o perati ons o n th e Co nt ain m en t Purge System; and (b) b ased on th ose predictions, use procedures t o co rr cct, co nt ro l , or miti ga t e th e co n seq uen ces of th ose malfuncti o ns o r o per a ti o n s: S tartup ope ra tio ns a nd th e associa ted requir e d va l ve lineup s R eference:

3-NO P-05 3 step 2.1.4 Question history: EXAMINER 1.1.24.39.3.1 Correct answer: C A In co rr ect; on l y 3V9 w ill trip. Pl a u s ibl e; expect CV I s ignal to i so l a t e Co ntainm ent. B In correc t; on l y 3V9 w ill trip. Pl ausible; ex pe ct CV I s i gna l to isolate Co ntai nment. C Correc t; on l y 3V9 trip s and Conta inm ent iso l a t ed. 4V20 s t opped to pr o t ect f a n. o In co rr ec l; 4V20 s topp ed to protect fan. Plausible; s toppin g purge exhaust f a n part of CV I. Cognitive l eve l: I Pa ge 116 of200 Question #59 ES-401 Question 59 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional)

RO 2 2 033A1.01 Transfer tube gate is closed and off-load just completed so at same level R-14 is not increasing

-no assembly failure SFP cooling leak would lower level, increasing ARM level Technical Reference(s)

5610-M-3060 sheet 1 10/16/2008 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided)

__________________

_ (including versionlrevision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: (As available)

Question Source: Bank# Modified Bank # New 1.1.25.40.2.4 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 x

Que s tion #59 ES-401 Qu e st io n 59 Wr i tten Examina t ion Question Workshee t Examination Outline Cross* Re f erence: L evel T ier # Group # KiA # I mportance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional)

RO _2_ _2_ 033A1.01 Tran s fer tub e gate i s cl ose d and o ff*l oa d ju s t co mp l eted so at sa me le v el R-14 i s not increa s ing -no assemb l y fai l ure SFP cooling l eak would l owe r l evel. increa s ing A RM le v el Technical Refere n ce(s): 5610*M*3060 sheet 1 1011612008 6/25120 09 Form ES-401*5 SRO (Attach if not previously provided)"..

_________________

_ (including ve r sion/revision nu m ber), ____________________ _ Proposed references t o be provided to applicants during examination

None Learning Objec t ive: (As ava il able) Question Source: Bank # Modified Bank # New 1.1.25.40.2.4 ==,,-(N o t e changes o r attach parent) Question H istory: L ast N RC Exam (Op t ional: Questions val idated at the facility since 10195 will generally undergo less rigorous review by Ihe NR C; failure to provide t he in f ormation will necessitate a detailed review of every question.) Question Cognitive L evel: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehe n sion or Analysis 55.41 _5_ 55.43 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam,xam Item: 1.1.25.40.2.4 9022400204

A refueling outage is in progress on Unit 4.

Core off-load was completed several hours ago and the fuel transfer tube gate is closed.

ARM -R-140BB (Unit 4 SFP Canal Area) and ARM-R-1422B (Unit 4 SFP South Wall) are indicating increasing radiation level trends, higher than expected.

PRMS-4-14 , Plant Vent Gaseous Monitor, shows no change in radiation level. What is the most likely cause of this condition?

A) One of the fuel assemblies was damaged during off-load 8) One of the fuel assemblies is leaking gases from a cladding penetration. C) Spent Fuel Pit level is decreasing due to a refueling cavity seal leak D) Spent Fuel Pit level is decreasing due to a Spent Fuel Pit Cooling System leak. CORRECT or INCORRECT feedback for item: 1.1.25.40.2.4 Transfer tube gate closed -no seal leak R-14 not increasing

-no assembly failure SFP cooling leak would lower level, increasing ARM levels Item Classification:

Analysis Item difficulty:

0.00 Keywords:

2.3.11 em weight: 10 oints required for mastery: 1 Correct alternative(s):

0 Judging values of alternatives:

A=-1 8=-1 C=-1 0=1 Uems in G:\Trng\Apps\VlJEXAM1NE\PTN Exam\PTN Exam_xam Item: 1.1.25.40.2.4 9022400204

A refueling outage is in progress on Unit 4.

Core off-load was completed several hours ago and the fuel transfer tube gate is closed.

ARM -R-1408B (Unit 4 SFP Canal Area) and ARM-R-1422B (Unit 4 SFP South WaH) are indicating increasing radiation level trends, higher than expected.

PRMS-4-14 , Plant Vent Gaseous Monitor , shows no c hange in radiation level. VVhat is the most likely cause of this condition?

A) One of the fuel assemblies was damaged during off-load B) One of the fuel assemblies is leaking gases from a cladding penetration. C) Spent Fuel Pit level is decreasing due to a refueling cavity seal leak 0) Spent Fuel Pit level is decreasing due to a Spent Fuel Pit Cooling System leak. CORREC T or INCORRECT feedback for item: 1.1.25.40.2.4 Transfer tube gale closed -no seal leak R-14 not increasing

-no assembly failure SFP cooling leak w ou ld lower level , in c reasing ARM le v els Ilem Classification

Analysis Ilem difficulty

0.00 Keywords: 2.3.11 em weight: 10 oints required for mastery: Correct altemative (s): 0 Judging values of alternatives

A=-1 8=*1 C=-1 0=1 06/25/2009 Turkey Point ILC 25 NRC Examination Question 59

A refueling outage is in progress on Unit 4.

Core off-load has just been completed.

The fuel transfer tube gate is closed.

ARM-R-1408B (Unit 4 SFP Canal Area) and ARM-R-1422B (Unit 4 SFP South Wall) are indicating increasing radiation trends, higher than expected.

PRMS-R-14, Plant Vent Gaseous Monitor , shows no change in radiation level. What is the most likely cause of this condition?

A One of the fuel assemblies was damaged during off-load. B One of the fuel assemblies is leaking gases from a cladding penetration. C Spent Fuel Pit level is decreasing due to leakage by the fuel transfer tube gate. D Spent Fuel Pit level is decreasing due to a Spent Fuel Pit Cooling System leak. Page 1170[200

06/25/2009 Turkey Point ILC 25 NRC Examination Question 59

A refueling outage is in Prob'TCSS on Unit 4.

Core off-load has just been completed.

The fuel transfer tube gate is closed.

ARM-R-1 408B (Unit 4 SFP Cana l Area) and ARM-R-1422B (Unit 4 SFP South Wall) are indi cating increasing radiation trends , higher than expected.

PRMS-R-14 , Plant Vent Gaseous Monitor, shows n o change in radiation level. What is the most lik e l y cause afthis condition?

A One of the fue l assemb li es was damaged during off-load.

BOne oflhe fuel assemblies is leaking gases from a cladding penetration.

C Spent Fuel Pit level is decreasing due to leakage by the fuel transfer tube gate. D Spent Fuel Pit level is decreasing due to a Spent Fuel Pit Coo ling System leak. Page 117 o f200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 59 KJA 033Al.Ol Spent Fuel Pool Cooling Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Spent Fuel Pool Cooling controls including:

Spent fuel pool water level

Reference:

561 0-M-3060 sheet 1 Transfer tube gate is closed and off-load just completed so at same level R-14 is not increasing

-no assembly failure SFP cooling leak would lower level, increasing ARM level Question history: EXAMINER 1.1.25.40.2.4 Correct answer: D A Incorrect per above discussion. Plausible; fuel damage would increase ARMs. B Incorrect per above discussion.

Plausible; fuel damage would increase ARMs. C Incorrect per above discussion.

Seal cavity leak would cause above. D Correct per above discussion. Cognitive level: 2 Have to analyze to determine failure. Page 1180[200

06/2512009 Turkey Point IL C 25 NRC Exam inati on Question 59 KJ A 033A 1.0 1 Spent Fucl Pool Coo ling Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Spe nt Fuel Pool Cooling con tr o l s including:

Spent fuel pool water level

Reference:

56 1 0-M-3060 sheet 1 Transfer tube gate is closed and off-load just comp l eted so at same le ve l R-J4 is not increasing

-no assembly failure SFP cooling l eak would lower le ve l , increasing ARM l evel Question history: EXAMfNER 1.1.25.40.2.4 Correct answer: D A in correct per above discussion.

Plausible; fuel damage would increase ARMs. B Incorrect per above discussion.

Plausible; fuel damage wo uld increase ARMs. C Incorrect per above discussion.

Sea l cavity leak would cause above. D Correct per above discussion. Cognitive level: 2 Have to ana l yze to determine failure. Page 11 80 f200 Question #60 ES-401 Question 60 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional)

RO _2_ 2 035A4.02 6/25/2009 Form ES-401-5 SRO Technical Reference(s):

5613-M-3074 sheets 2 & 3 03/27/2007

& 04/09/2009 (Attach if not previously provided) 5613-M-3075 sheet 2 03/06/2000 (including version/revision number) 3-EOP-FR-H

.1 caution before step 4 12/12/2008 BD-EOP-FR-H

.1 caution before step 4 12/12/2008 Proposed references to be provided to applicants during examination

None Learning Objective: .=..69.=...0=2=..:3o..;::3;..:..7_0=..b=..i,,-.

4...:-__________ (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach parent) New X Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X Question #60 ES-401 Question 60 Written Examination Question Worksheet Examination Outline Cross-Reference

L evel Tier # G r o up # KIA # Im po rta nce Rating Proposed Ques t ion: See attached Proposed Answe r: A E xplanation (Op tional): 6/25 12 009 Form ES-401-S RO SRO _2_ --_2_ --035A4.02 ..1L Tec h nica l Reference(s)

56 1 3-M-3074 sheets 2 & 3 0312712007

& 0 4 10912009 (Attach i f not previo usl y provided) 5613-M-3075 sheet 2 0310612000 (i ncluding ve r sio n/revision numb e r) 3-E O P-FR-H.1 ca uti on before step 4 12/1 2/2008 BO-E OP-FR-H.1 caution be fore step 4 12 1 1 212008 Proposed references t o be provided to applicants during e x amination: Non e L earning Objective: "6"'90"'2,,3"'3CL7-'O"'b,,i"'4"---

_________ (A s av ailable) Question So u rce: Bank# Modified Bank # --c-(N o te changes or attach parent) New X Question Hi story: Last NR C E xam (Optional: Questions validated at/he facility since 10/95 will generally undergo less rigorous review by the NRC; f ailure t o provide the informat i on will necessitate a detailed review o f every question)

Question Cognitive L eve l: 10 CFR Part 55 Content: Commen t s: Memory or Fundamental Knowledge Compre h ens i on o r Analysis 55.41 _7_ 55.43 x 06/2512009 Turkey Point ILC 25 NRC Examination Question 60

The Unit 3 crew is performing 3-EOP-FR-H.l, Response to Loss of Secondary Heat Sink.

The BOP is preparing to feed the S/Os using the B Standby Steam Oenerator Feedpump.

All wide range S/O levels are less than 3% and steady.

RCS hot leg temperatures are 580°F and increasing.

How should the BOP control feed flow to the Steam Generators?

The BOP should initially

... A use change in Thots. Feed flow indication is not accurate in the range required.

B use change in Thots. Bypass Feed flow is not seen by feed flow transmitters.

C establish less than 100 gpm flow to each S/O using AFW flow indication. Main Feed flow indication is not accurate in the range required.

D establish less than 100 gpm flow to each S/O using AFW flow indication.

Bypass Feed flow is not seen by the Main Feed flow transmitters.

Page 119 of 200

06/25/2009 Turk ey Point LL C 25 NRC Examination Question 60

The U nit 3 crew i s perfonning 3-EOP-FR-H.I , R espo n se to Loss of Secondary H eat S ink.

The BOP i s pr e parin g to feed th e S I Gs u si ng t he B Standby Steam Generator Feedpump.

A ll wide range S/G l evels are le ss than 3% a nd s tead y_

Res h ot le g temperature s are 580°F and increasing.

H ow s hould th e BOP co ntr o l feed flow t o the Steam Generators?

The BOP s hould initiall y ... A u se c han ge in Thols. Feed flo w indication i s not accurate in the range r e quired. B usc cha n ge in Thets. Byp ass Feed fl ow i s not see n by feed flo w transmitters.

C es t ab li sh J ess than 1 00 gpm flow to each S/G u s in g AFW flo w indicati o n. Main Feed fl ow indi ca tion i s not acc ur ate in the r ange r eq uir ed. o es t ab li sh l ess than 100 gpm flo w to eac h S/G using AFW fl ow indi ca t ion. Bypa ss F eed fl ow i s n o t see n by the Main Feed n ow tran s mitter s. P age 1 1 90[200 06125/2009 Turkey Point ILC 25 NRC Examination Question 60 KJ A 035A4.02 Stearn Oenerator Ability to manually operate and/or monitor in the control room: Fill of dry S/O

Reference:

5613-M-3074 sheets 2 & 3 5613-M-3075 sheet 2 3-EOP-FR-H.l CAUTION before step 4 BD-EOP-FR-H.l CAUTION before step 4 Question history: New Correct answer: A A Correct; per CAUTION -low flows not accurate on MFW flow indications and use change in RCS temperatures and S/O level. B Incorrect; bypass flow seen by MFW flow transmitters.

Plausible; need to know flow schematic.

C Incorrect; need to use MFW flow indications.

Plausible; normally use AFW flow indications and procedure calls for less than 100 gpm to dry S/O. D Incorrect; MFW flow indications not accurate at low flow and should use Thot or S/O changes. Plausible; procedure sets limit. Cognitive level: 2 Need to apply CAUTION Page 120 of 200

06/25/2009 Turkey Point IL C 25 NRC Examination Q u est i o n 60 KIA 035A4.02 Stea m Generator Ability t o manu a ll y opera te a n d/or moni tor in th e con trol r oo m: Fill o f dry S/G Ref ere n ce: 56 1 3-M-3074 s he ets 2 & 3 56 1 3-M-3075 shee t 2 3-EOP-FR-H.

1 CAU TIO N before s tep 4 BD-EOP-FR-H

.I CAUT I ON before step 4 Ques ti on history: New Correct answer: A A Correct: per CAU TIO N -l ow fl ows not accurate o n MFW fl ow indi ca tion s and u se c h a n ge in ReS t e mp e r a ture s and S/G l eve l. B In correct; bypass flow seen by MFW fl ow transmitters.

P l a u sib l e; n eed t o know fl ow sc h ema ti c. C In correc t; n eed to use MFW fl ow indi ca ti o n s. Pl a u s ibl e; nonna ll y use AFW fl ow in di catio n s and procedure calls for l ess th an 100 gpm to dry S/G. D I ncorrec t; MFW fl ow in di cat i o n s not accurate at l ow fl ow and s h o uld use Th ot o r S/G changes. Plausible: procedure sets limit. Cognitive l evel: 2 Need t o ap pl y CAUT I ON P age 120 o f 200 Question #61 ES-401 Question 61 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: o Explanation (Optional):

lAW PCB , Tavg at 40% power is 557.9°F RO 2 2 045K4.44 Turbine trip with T a vg greater than 554.5°F will f a st open two valve s. Turbin e trip with Tavg great e r than 561.5°F will fast open four valve s. 6/25/2009 Form ES-401-5 SRO Technical Reference(s):

561 O-T-L 1 sheets 22 A&8 01/20/1998

& 08/24/2006 (Attach if not previously provided)

PCB Section IV Fig. 5 12/15/2008 (including version/revision number), ___________________

_ Proposed references to be provided to appl i cants during examination:

None Learning Objective: 6902118 Obj. 7 (As available)

Question Source: Bank # Modified Bank # New 1.1.24.18.5.7

___ (Note changes or attach parent) Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the i nformation w i ll necessitate a detailed review of eve!}' question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x Question #61 ES-401 Question 61 Written Examination Question Worksheet Examination O uttine Cross-Reference

Level Tier # Group # KiA # Importance Rating Pr opose d Question: See attached Proposed Answer: D Explanation (Optiona l): lAW PCB , Tavg at 40 0/0 power is 557.9°F RO 2 2 045K4.44 Turbine trip with Tavg greater th an 554.5°F will fast ope n two va lv es. Turbine trip with Tavg greater than 561.5°F w ill fast open four va l ves. 6/25/2009 Form ES-401-5 SRO ----...£IL Technical Reference(s):

5610-T-L 1 sheets 22 A&B 01/20/1998

& 08/24/2006 (Attach if not previously provided)

PCB Section IV Fig. 5 12/15/2008 (in cluding ve rsion/revi s ion number) __________________

_ _ Proposed references t o be provided to applicants during examina tion: Non e Learning Objective: 6902118 Obi. 7 (As available)

Question Source: Bank # Modified Bank # New 1.1.24.18.5.7 --.,-..,..,,,-(Note changes or attach parent) Question History: Last NR C E xam (Optional: Quest i ons v8lidated at the facility since 10195 will generally undergo less rigorous review by the NRC: fa i lure to p rovi de the infonnat i on will necessitate a detailed rev i ew of every question) Question Cognitive Le vel: 10 CFR Part 55 Content: Comments: Memory o r Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.1B.5.7 9021180507

Unit 3 reactor power is steady at 40%.

Turbine First Stage Pressure Transmitter PT-3-447 has just failed high.

The turbine subsequently trips. How will the steam dumps to condenser operate? A) None of the valves will open 8) All four valves will trip full open C) All four valves will modulate open D) Two valves will trip full open and two valves will modulate open CORRECT or INCORRECT feedback for item: 1.1.24.1B.5.7 Tavg for 40% power is approx 558F. This fast opens two valves. (4 fast open if Tavg > 561 F) Arming signal from turbine trip, not affected by 447 failure Item Classification:

Analysis Item difficulty:

0.00 Keywords: 041 A4.0B Item weight: 10 Points required for mastery: 1 Correct alternative(s):

D u dging values of alternatives:

=-1 8=-1 C=-1 D=1 liems in G:\TrnglApps\WEXAMINE\PTN Exam\PTN Exam , xam Item: 1.1.24.18.5.7 9021180507

Unit 3 reactor power is steady at 40"/".

Turbine First Stage Pressure Transmitter PT-3-447 has just failed high.

The turbine subsequently trips. How will the steam dumps to condenser operate? A) None of the valves will open B) All four valves will trip full open C) All four valves will modulate open D) Two valves will trip full open and two valves will modulate open CORREC T o r INCORRECT feedback for item; 1.1.24.18.5.7 Tavg for 40% power is approx 558F. This fast opens two valves. (4 fast open if Tavg > 561F) Arming signal from turbine trip , not affected by 447 failure Item Classification

Analysis Item difficulty

0.00 Keywords:

041 A4.08 Item weight: 10 Points requ ire d for mastery: 1 Co rrect alternative(s

): 0 dging values of alternatives

=-1 8=-1 C=-1 D=1 06/25/2009 Turkey Point ILC 25 NRC Examination Question 61

Unit 3 is steady at 40% power.

Turbine First Stage Pressure Transmitter PT-3-447 has just failed high.

The turbine subsequently trips. How will the Steam Dumps to Condenser operate? A None of the valves will open. B All four valves will trip full open. C Two valves will trip full open and two valves will remain shut. D Two valves will trip full open and two valves will modulate open. Page 121 0[200 06/25/2009 Turke y P o int IL C 25 NRC Examination

Question 61

Unit 3 i s steady at 40% power.

T urbin e First Stage Pressure Transmitter PT*3-447 has just fai l ed high.

The turbine subsequent l y trip s. How will the Steam Dump s to Condenser ope rat e? A None of the valves will open. B All four valves will trip fuJI o pen. C Two va l ves wi ll trip full open and two va l ves will rema in shut. o Two valves wi ll trip full open and two valves will modulate open. Page 121 of200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 61 KIA 045K4.44 Main Turbine Generator:

Knowledge of Main Turbine Generator design features and/or interlocks which provide for the following:

Impulse pressure mode control of steam dumps

Reference:

561O-T-L1 sheets 22A1B Plant Curve Book (PCB)Section IV Figure 5 lAW PCB, Tavg at 40% power is 557.9°F Turbine trip with Tavg greater than 554.5°F will fast open two valves. Turbine trip with Tavg greater than 561.5°F will fast open four valves. Question history: EXAMINER 1.1.24.18.5.7 Correct answer: D A Incorrect per reference and discussion.

Plausible; 447 failing high prevents 447 arming, but arming is from turbine trip. B Incorrect; two valves will trip open and two will modulate in open direction.

Plausible; four valves will trip open ifTavg greater than 561°F. C Incorrect; two valves will trip open and two will modulate in open direction.

Plausible; error signal is high enough to modulate valves open. D Correct per above reference and discussion. Cognitive level: 3 Need to calculate Tave for 40% power, realize turbine trip effect, and determine number of valves that will trip open. Page 122 of 200 06/25/2009 Tur key P oint IL C 25 N RC Examination Question 61 KIA 045K4.44 M ai n Turbine Gene rat o r: Knowledge o f Main Turbine Generator design feature s a nd/o r int erloc k s which pro v id e for th e following:

Impul se pressure mode co ntr o l of steam dumps

Reference:

56\o-T-LJ s hee ts 22N B Plant C ur ve Book (PCB)Section I V Fi gu re 5 I A W P C B , Tavg at 40% power i s 557.9°F Turbine trip w ith Tavg greate r than 554.5°F wi ll fast open t wo va l ves. Turbin e trip wi th Tavg greater than 56 1.5°F will fast o pen four va lv es. Question hi s tor y: EXAMINER 1.1.24.18,5.7 Correct answer: 0 A In co rr ec t per reference an d discussion.

Plausible; 447 f ai ling hi g h pr events 447 anni o g , but a nnio g is from turbine trip. B In co rr ec t; two va l ves w ill trip open a nd two will modul ate in open dire ction. Plau s ibl e; four va l ves w ill trip open ifTa vg greate r t han 56 1°F. C In co rr ec t; t wo va l ves will t rip ope n a nd two w ill modulate in o p en direction. Pl a u s ibl e; error s i gnal i s high enough to m od ul ate va l ves open. D Correc t per above r efe ren ce a nd discussion.

Cogni ti ve l eve l: 3 Need to c alcu l a t e Tave for 40% power, r ea li ze turbine trip effect, and det e nnine numb e r of va l ves that wi ll tri p ope n. Page 1 220(200 Question #62 ES-401 Question 62 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

RO 2 2 055K3.01 Technical Reference(s)

4-0NOP-014 Enclosure 1 03/06/2008 (Attach if not previously provided) 4-NOP-073.01 04/17/2009 (including versionlrevision number) LP 6902131 pp. 33 & 63 07/31/2007 Proposed references to be provided to applicants during examination

None Learning Objective:

6902131 Obi. 10 (As available)

Question Source: Bank# 6/25/2009 Form ES-401-5 SRO Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of eve/}' question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 --X

Question #62 ES-401 Question 62 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Imp orta nce Rating Proposed Question: See atta ched Proposed Answer: A Explanation (Optional)

RO 2 2 055K3.01 Technical Reference (s): 4-0NOP-014 Enclosure 1 03/06/2008 (A ttach if not previously provided) 4-NOP-07 3.01 0 4/17/2009 (including version/revision number) LP 6902131 PD. 33 & 63 07/31/2007 6/2 5/2009 Form ES-401-5 SRO Pr oposed references to be provided to applicants during examination:

None L earning Objective: 6902131 Obj. 10 (As available)

Questio n Source: Bank# Modified Bank # New __ :-;-(N ote changes or attach parent) X Question Hi story: Last NRC Exam (Optional: Questions validated at Ihe facility since 10195 will generally undergo less rigorous raview by Ihe NRC: failure to provide the information will necessi tat e a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension o r Analysis 55.41 _7_ 55.43 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 62

Unit 4 was initially at 100% power.

A leak developed on the steam supply to the Steam Jet Air Ejectors.

The crew placed the hogging jet in service and isolated the leak. In accordance with 4-0NOP-014, Main Condenser Loss of Vacuum, how will plant operations be affected by the above incident?

A The unit can remain at 100% reactor power. Generated megawatts will be less. B The unit can remain at 100% reactor power. Generated megawatts will be the same. C The crew shall reduce load and stabilize power at a lower value. D The crew shall trip the reactor and turbine. Page 123 of 200 06 1 25 1 2009 Turkey Point ILC 25 NRC Examination Question 62

Unit 4 was initially at 100% power.

A leak developed on the steam supply to the Steam Jet Air Ejectors.

The crew placed the hogging jet in service and isolated the leak. In accordance with 4-0NOP-014, Main Condenser Loss of Vacuum, how will plant operations be affected by the above incident?

A The unit can remain at 100% reactor power. Generated megawatts will be less. B The unit can remain at 100% reactor power. Generated megawatts will be the same. C The crew shall reduce load and stabilize power at a lower value. D The crew shall trip the reactor and turbine. Pa ge 1 23 o f 20 0 06/25/2009 Turkey Point ILC 25 NRC Examination Question 62 KIA 055K3.01 Condenser Air Removal Knowledge of the effects that a loss or malfunction of the Condenser Air Removal System will have on the following:

Main Condenser

Reference:

4-0NOP-014 Enclosure 1 4-NOP-073.1 LP 6902131 pp. 33 & 63 Question history: New Correct answer: A A Correct; lAW LP 6902131 the hogging jets can maintain 25" vacuum, which is within 4-0NOP-014 Enclosure

1. B Incorrect; vacuum will be less, so MWe will be less. Plausible; need to realize vacuum will be less and effect. C Incorrect; within values of Enclosure

1. Plausible; lost SJAEs. D Incorrect; within values of Enclosure

1. Plausible; lost SJ AEs. Cognitive level: 2 Need to analyze for effect oflosing SlAEs and placing hogging jet in service. Then need to compare vacuum can maintain to Enclosure 1 Page 1240[200

06/25/2009 Turke y Point IL C 25 N R C Exami nati o n Question 62 KIA 055K3.01 Co nd e n se r A ir R e m ova l Knowledg e of th e effects th at a lo ss or malfunction of the Co nden se r A ir Remo va l Sys tem will have o n th e f o ll owi n g: Main Condense r

Reference:

4-0NOP-0 1 4 Enc l os ur e I 4-NOP-073.1 LP 6902131 pp. 33 &63 Quest i on hist ory: New Co rrect answer: A A Co rre c t; l AW LP 6902 1 3 1 th e h ogging j e ts ca n maintain 25"' vac uum , which i s w ithin 4-0NOP-014 Enclosur e I. B In co rre c t; v acuum will be le ss. so MWe wi ll be l ess. Plau s ibl e; n eed t o reali ze vacu um w ill b e l ess and effec t. C In co rre c t; within va lu es of E n c10s ur e I. Pl a u si ble; l os t S J AEs. D In coITect; wit hin values of Enclosure

1. Pl a u s ible; l ost S JAE s. Cogni t ive level: 2 Ne ed to ana l yze for effect of losing S J AEs and placing h oggi ng je t in service. Then n ee d to co mpar e vac uum ca n maintai n to E ncl os ure 1 P ag e 124 o f200 Question #63 ES-401 Question 63 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: D Explanation (Optional):

RO 2 2 068A3.02 6/25/2009 Form ES-401-5 SRO R-014 high seals in. R-018 does not seal in. RCV-014 cannot be re-opened until hand loader on WPB set to ze ro. Technical Reference(s)

5613-E-25 sheet 88A 08/12/1997 (Attach if not previously provided)561 0-M-420-165 03/09/1991 (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902168 Obi. 4 (As available)

Question Source: Bank# 1.1.24.49.6.10 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 This is a substitute KIA. KIA 068A3.02 is N/A to PTN x

Question #63 ES-401 Question 63 Written Examination Question Worksheet E xami nation Outline Cross-Reference

L evel T i er# Group # KIA # I mportance Rating Proposed Question: See attached Pr oposed Answer: D Explana ti on (Op t io nal): 6/2 5/2009 Form ES-401-5 RO SRO 2 --2 --068A3.02 R-O 1 4 high sea l s in. R-O 18 does not sea l in. R e V -0 14 cannot be r e-ope n ed u n til hand l oader on WPB set t o zero. T echnica l Reference (s): 5613-E-25 sheet 88A 08/12/1997 (A tta c h if not previous l y provided)56 1 0-M-420-165 03/09/1 99 1 (i nclud i n g versio n/revi sion number), ___________________

_ Pr oposed r e fer ences to be provided to appli ca nts du r ing examination:

None Learning Objective: 6902168 Obi. 4 (As available) Question Source: Bank # 1.1.24.49.6.1 0 M odifie d Bank # __ ::-(Note changes or attach pa r ent) New Question H istory: La s t NRC E xa m (Oplional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a de/ailed review of every question)

Question Cognitive L evel: 10 C F R Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 Th is is a substitute KIA. KIA 068A3.02 is N/A to PTN x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.49.6.10 9021490610

A liquid release and a gas release are in progress.

The power supply breaker to PRMS Rack 3QR66 is opened due to a clearance error and the SM authorizes reclosun of the breaker to re-energize the rack. How will RCV-014 and RCV-018 respond when the RCO resets the Hi Alarm on the respective PRMS drawers? (Assume no actions were taken prior to resetting the alarms) NOTE: RCV-014 is Gaseous Release Header Isolation Valve RCV-018 is Liquid Release Header Isolation Valve A) Both RCV-014 and RCV-018 will reopen 8) Both RCV-014 and RCV-018 will remain closed C) RCV-014 will reopen and RCV-018 will remain closed D) RCV-014 will remain closed and RCV-018 will reopen Item Classification:

Comprehension Item difficulty:

0.00 Keywords:

RCO, SRO Item weight: 1 Points required for mastery: 1 Correct alternative(s):

D udging values of alternatives

=-1 8=-1 C=-1 D=1 Items in G:\Trng\.A,pps\WEXAMINE\PTN Exam\PTN Exam.x am I tem: 1.1.24.49.6.10 902 1 490610

A liquid release and a gas release are in progress.

T he power supply breaker to PRMS Rack 3QR66 is opened due t o a clearance e r ror a n d the SM authorizes rectosun of the b r eaker to re-energize t h e rack. How will RCV-014 and RCV-01B r espond when the RCO resets the Hi Alarm on t h e r espective PRMS drawers? (Assum e no ac t ions were taken prio r to resetting the alarms) N O T E: RCV-014 is Gaseous Release H eader I solation Valve RCV-01B is liquid Release Header I solation Valve A) Both RCV-0 1 4 and RCV-01B will reopen B) Both RCV-014 and RCV-01B will remain closed C) RCV-014 will reopen and RCV-01B will remain closed D) RCV-014 will remain closed and RCV-018 will reopen Item Classification:

Comprehension Item difficulty

0.00 Keywords: RCO. SRO Item w e ight: 1 Points r equi re d fO I mastery: 1 Correct allernative(s)

0 *udgin g values o f alterna\lves

=-1 8=-1 C=--1 0=1 06/25/2009 Turkey Point ILC 25 NRC Examination Question 63

A liquid release and a gas release are in progress.

The power supply breaker to PRMS Rack 3QR66 is opened due to a clearance error.

The Shift Manager authorizes reclosure of the breaker to reenergize the rack. How will RCV-014 and RCV-018 respond when the RO resets the Hi Alarm on the respective PRMS drawers? NOTE: RCV-014 is Gaseous Release Header Isolation Valve RCV -018 is Liquid Release Header Isolation Valve RCV-014 RCV-018 A Re-opens Re-opens B Remains closed Remains closed C Re-opens Remains closed D Remains closed Re-opens Page 1250[200

06/25/2009 Turkey Point lL C 25 NRC Examination Que s tion 63

A liquid release and a gas release are in progress.

The power supp l y breaker t o PRMS Rack 3QR66 is opened due to a clearance error.

The Shift Manager authorizes rcclosure of the breaker to reenergize th e rack. How w ill RCV-014 and ReV-DIS respond when the RO re sets the Hi A lann on the respecti v e PRM S drawers? NOTE:RCV-OI4 i s Gaseous Releas e Header I so l ation Valve ReV-DIS i s Liquid Release H eader I so lati on Valve RCV-OI4 RCV-018 A Re-opcns Rc-opens B Remains closed Remains closed C Re-opens Remains closed D Remains closed Re-opens Pa ge 1 25 o f 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 63 KJ A 068A3.02 Liquid Radwaste Ability to monitor automatic operation the Liquid Radwaste System including:

Automatic isolation NOTE: This is a substitute KJA

Reference:

5613-E-25 sheet 88A -R-014 high seals in 5610-M-420-165

-R-018 does not seal in RCV-014 cannot be re-opened until hand loader on WPB set to zero. Question History: EXAMINER 1.1.24.49.6.10 Correct answer: D A Incorrect; RCV-014 will not re-open. Plausible; need to know that RCV-014 requires hand loader set to zero. B Incorrect R-018 will re-open. Plausible; this is the safe mode C Incorrect this is the reverse of what happens. Plausible; confusing RCV-014 with RCV-018 D Correct per above reference and discussion Cognitive level: 1 Page 126 of 200 06/25/20 0 9 Turkey Point IL C 25 N R C Examination Quest i o n 63 KIA 068A3.02 Liquid Rad was te Ability to m o nit o r automatic ope rati o n the Liquid R a dw as t e Sys t em includin g: A utom a tic i so lati o n NO TE: Thi s i s a subs titut e K/ A Re fe rence: 5613-E-25 s he et 88A -R-0 1 4 high sea l s in 5610-M-420-165

-R-01 8 d oes not sea l in R CY-0 14 can n o t b e fe-opened until hand l oa der o n WPB set t o ze ro. Ques ti on Hi s t ory: EXAM I NE R 1.1.24.49.6.10 Co n-eel answer: D A In co rr ec t; R CV-OI 4 will not f e-opc n. Pl a u s ible; need to k n ow that R CV-014 requir es h and l oa d e r se t to ze ro. 8 In co rr ect R-018 w ill re-opcn. Pl a u s ible; thi s i s th e safe m o d e C In correc t thi s is the reverse of what happen s. Plau s ible; confusing R CV-OI4 with R ev* 0 1 8 o Co rre c t per above r efere n ce a nd di sc u ss i on Cogn i t iv e le v el: I Pag e 1 26 of200 Question #64 ES-401 Question 64 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional):

Technical Reference(s)

5610-T-L 1 sheet 11 04/09/2009 (Attach if not previously provided) 3-0NOP-067 Att. 1 09/27/2007 RO 2 2 072K1.04 6/25/2009 Form ES-401-5 SRO (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective:

6902168 Obi. 7 (As available)

Question Source: Bank # Modified Bank # New 1.1.24.68.6.14 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to prov i de the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x Question #64 ES-401 Question 64 Written Examination Question Worksheet Examination Ou tl ine Cross-R eference: Le vel Tier # Group # KIA # I mporta n ce Rating Proposed Question: See attached Prop osed Answer: A Explanation (Op t ional): T echnical Reference(s)

5610-T-L 1 s heet 11 0 4 10912009 (A ttach if not previously provided) 3-0 NOP-067 At! 1 0912712007 6/2512 009 Form ES-401*5 RO SRO 2 --2 --072K1.04 (inc lud i ng ve r sion/revision number) ___________________

_ Proposed references t o be provided to applicants du ri ng examination:

N one L earning Objective: 6902 1 68 Obi. 7 (As available)

Question Source: Bank # Modified Bank # N ew 1.1.24.6 8.6.14 _---,,,-(No te c hange s or attach parent) Ques t ion H istory: Last NR C Exam (Optional: Questions validated at the facility since 10/95 will generally undergo less rigorous review by th e NRC; failure to pm0de the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Conten t: Comments: Memory Of Fundamental K nowledge Com pr ehension or Analysis 55.41 _7_ 55.43 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.68.6.14 9021680614

Which one of the following describes the response of the Control Room Ventilation System to a high radiation alarm on the Control Room Ventilation System Radiation Monitors, RAD-6642 or RAD-6643?

Outside Air Dampers Kitchen and D-1A & D-1B Lavatory Fans A) Close Stop 8) Close Start C) Open Stop 0) Open Start Item Classification

Comprehension Item difficulty

0.50 Keywords: NLOCT , SNPO Item weight: 10 Points required for mastery: 1 Correct alternative(s)

A Judging values of alternatives

A=1 8=-1 C=-1 0=-1 Memo Field:

REFERENCE:

SO-068 KA: 072000K104

[3.3/3.5]

OL: 200 Emerg. Recirc. Fan SF-1 B Start Start Stop Stop Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.68.6.14 9021680614

IM1ich one of the following describes the response of the Control Room Ventilation System to a high radiation alarm on the Control Room Ventilation System Radiation Monitors , RAD-6642 or RAD-6643?

Outside Air Oampers Kitchen and D-1A&D-1B Lavatory Fans A) Close Stop 8) Close Start C) Open Slop D) Open Start Item Classification

Comprehension Item difficulty

0.50 Keywords: NLOCT , 8NPO Item weight: 10 Po i nts required for 1 Correct aliernalive(s)

A Judging values of alternatives

A=1 8=-1 C=-' 0=-1 Memo Field:

REFERENCE:

80-068 KA 072000K104

[3.3 1 3.5] OL: 200 Emerg. Recirc. Fan SF-1B Start Start Stop Stop 06/25/2009 Turkey Point ILC 25 NRC Examination Question 64 In accordance with 3-0NOP-067, Radioactive Effluent Release, which one of the following describes the response of the Control Room Ventilation System to a high radiation alarm on the Control Room Ventilation System Radiation Monitors, RAD-6642 or RAD-6643?

Kitchen and Emerg. Ventilation Lavatory Fans Supply Fan A Stop Start B Start Start C Stop Stop D Start Stop Page 127 0[200

06125/2009 Turk ey P o int IL C 25 N R C Exa min a ti on Quest i o n 6 4 In acco rdan ce wit h 3-0NO P-0 67, Radioactive E fflu e nt Release, which o ne o f the following de sc rib es the re s p onse of the Contro l Room Ve ntil ation Sys t e m to a high r ad i at i o n a l ann on th e Co ntr o l Ro o m Ven til a ti o n Syste m Radiation Mon i tors, RAD-6642 or RAD-6643?

Kitchen and Emerg. Ve ntilati on La va t o r y Fans Supply Fan A Stop S t art 8 S t ar t Start C S t op Stop D S t art Stop P a g e 1 27 o f 2 00 06125/2009 Turkey Point ILC 25 NRC Examination Question 64 KIA 072K1.04 Area Radiation Monitoring Knowledge of the physical connections and/or cause-effect relationships between the Area Radiation Monitoring System and the following system: Control Room Ventilation

Reference:

561 O-T -Ll sheet 11 3-0NOP-067 Attachment 1 Question history: EXAMINER 1.1.24.68.6

.14 modified Correct answer: A A Correct per reference B Incorrect per reference.

Plausible; need to determine which fans start and stop. C Incorrect per reference.

Plausible; need to determine which fans start and stop. D Incorrect per reference.

Plausible; need to determine which fans start and stop. Cognitive level: 1 Page 1280[200

06/25/2009 Turkey Point IL C 25 NRC Exa min ation Question 64 KIA 072K 1.04 Area Radiation Monitori n g Know l edge of the phy sica l connections and/or cause-effec t relationships between the Area Radiation Monitori n g System and the follow i ng system: Contro l Room Venti l at i on Referen ce: 56 1 0-T-LI s h eet II 3-0NOP-067 Attachment I Question hi s tor y: EXAM INER I. 1.24.68.6.14 modified Co rrect answer: A A Correc t per refer ence B In correct pe r referen ce. Plau s ible; need to determine wh i ch fans s tart and stop. C I ncorrect pe r refe r e n ce. P l aus i b l e; need to determi n e which fa n s sta rt and stop. o In correct per reference. Pl ausible; need to determine which fans s t art and s top. Cognitive le ve l: I Pa ge 1 28 o f 200 Question #65 ES-401 Question 65 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier# Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

Technical Reference(s)

5610-T-E-1591 sheet 1 7/6/06 RO 2 2 075K2.03 (Attach if not previously provided) 5613-T-L 1 sheets 12/12A112B 10/03/96 6/25/2009 Form ES-401-5 SRO --(including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902956 Obi-2 (As available)

Question Source: Bank # Modified Bank # New 1.1.24.54.6.5 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional. Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 x Ques ti on #65 ES-401 Question 65 Written Examination Question Worksheet E xamination Outline Cross-Refe rence: L evel Tier # Group # KIA # Im portance Rat i ng Pr oposed Question:

See attached Proposed Answe r: C Explanation (Optiona l): Technical Reference(s

): 56 1 0-T-E-1591 she et 1 7/6/06 RO _2_ 2 075K2.03 (A ttach if n ot previous l y provided) 5613-T-L 1 sheets 12/12A112B 10 103/96 6/25 1 1009 Form ES-401-5 SRO (i n cluding version/revision n u mber) ____________________

_ Pr oposed references to be provided to applicant s during examina t io n: N o n e Lea rning Objective: 6902956 Obi. 2 (As available)

Question Source: Ba nk# Modified Ban k # New 1.1.24.54.6.5 __ ,,-(N o te c hang es or atta c h parent) Question H istory: L ast NRC E xam (Optional: QUestions validated at the facility since 1Clf95 wit! generally undergo less rigorous review by the NRC: fa ilure to provide the informa tion w if/ necessitate a detailed review of every question.) Q ue st ion Cogn it ive Le vel: 10 CFR Part 55 Content:.

Comments: Memory or Fund a mental Knowledge Comp r ehension or Analysis 55.41 55.43 7 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.54.6

.5 9 021540605

Unit 3 is in Mode 1, 100% power

3D 4kV bus aligned to 3B 4kV bus.

All equipment is operable.

3A & 3C ICW pumps are running.

The unit undergoes a Safety Injection initiation with a loss of voltage on 3B 4KV Bus only. Which ONE of the following is correct? A) 3A and 3C ICW pumps will be stripped.

3A and 3B ICW pumps will receive start signals from the Sequencers.

8) 3A and 3C ICW pumps will be stripped.

3A and 3C ICW pumps will receive start signals from the Sequencers.

C) Only 3C ICW pump will be stripped. 3A and 3B ICW pumps will receive start signals from the Sequencers.

0) Only 3C ICW pump will be stripped. 3A and 3C ICW pumps will receive start signals from the Sequencers. Item Classification:

Comprehension Item difficulty

0.50 Keywords: LOP , NLOCT, STA , 076 K4.02 Item weight: 10 Points required for mastery: 1 Correct alternative(s)

C Judging values of alternatives

A=-1 8=-1 C=1 0=-1 emo Field:

REFERENCE:

SD-165 and SO-170 Items in G:\T rn glApps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.54.6.5 02 1 540605:

U nit 31s in Mode 1 , 100% powe r

3D 4 kV bus aligned to 38 4kV bus.

A ll equipment is operable.

3A & 3C l ew pumps are r unning.

Th e unit undergoes a Safety I njection iniliation with a loss of vol t age on 3B 4KV Bus o n ly. \,/\/hich ONE of t he following is cor r ect? A) 3A and 3C I CW pumps will be stripped. 3A and 38 I CW pumps will rece i ve start signa ls from the Se qu encers. B) 3A and 3C I CW pumps will be s tr ipp ed. 3A and 3C l ew pumps w ill receive start signals from the Sequencers. C) Only 3C l ew pump will be stripped , 3A and 38 ICW pumps will receive start signals from the Seque n ce r s. D) Only 3C I CW pump will be str i pped , 3A and 3C I CW pumps will r eceive s ta rt signals from the Seq u encers. I te m Classification

Comprehension Item difficulty

0.50 Keywords: lOP , NlOCT , 8TA, 076 K4.02 Item weight: 10 Points required for mastery: 1 Correct alternative(s)

C Judging values o f alternatives

A=*l 8=-1 C=l 0=*1 m o Fiel d: REFEREN CE: 80-165 and 80-170 06/25/2009 Turkey Point ILC 25 NRC Examination Question 65 Initial conditions:

Unit 3 is at 100% power.

3A and 3C ICW Pumps are running. Subsequently:

Unit 3 experiences a safety injection actuation with a loss of voltage on the 3B 4kV Bus only. How will the lew Pumps be affected?

A 3A and 3C ICW Pumps will be stripped.

3A and 3B ICW Pumps will receive start signals from the Sequencers.

B 3A and 3C ICW Pumps will be stripped.

3A and 3C ICW Pumps will receive start signals from the Sequencers.

C Only 3C ICW Pump will be stripped.

3A and 3B ICW Pumps will receive start signals from the Sequencers. o Only 3C ICW Pump will be stripped.

3A and 3C ICW Pumps will receive start signals from the Sequencers.

Page 129 of 200

06/25/2009 T urk ey Point IL C 25 N R C Examinati o n Qu es ti o n 65 I niti a l c o nditi o n s:

Unit 3 i s at 1 0 0% p o w er.

3A an d 3C l e w Pumps a re runnin g. S ub se qu e nt l y:

U nit 3 e xperi e n c es a sa f e t y inj ec ti on a c tuati o n w ith a l oss o f vo lta g e on the 38 4kV Bus o n l y. H ow w i ll th e l e W Pump s be a ffe c ted? A 3A a nd 3C I C W Pump s wi ll b e st ripped. 3 A a nd 3 8 l e W Pump s will r ec ei ve s t a rt s i gn al s fr o m the Se quencer s. B 3A a nd 3 C l e w Pumps w ill be s tripp e d. 3A a nd 3C l e w Pumps w ill r ece i ve s t a rt s i gna l s from t he S e q u e n ce r s. C Onl y 3C I C W Pump will be s.ripped. 3A a nd 38 l ew Pumps w i ll r ec e iv e s tart s ign a ls f r o m th e Se qu e n ce r s. D Onl y 3C I C W Pump w ill be stripped. 3A a nd 3C l e w Pump s w ill re c ei ve s tart s ignal s fro m th e Se quen c er s. P age 1 29 o f 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 65 KJ A 075K2.03 Circulating Water Knowledge ofthe bus power supplies to the following:

Emergency/essential SWS pumps

Reference:

561O-T-E-1591 sheet 1 5613-T-LI-12, 12A, 12B Question history: EXAMINER 1.1.24.54.6.5 Correct answer: C A Incorrect; stripping signal only goes to bus with loss of voltage. Plausible; need to realize only busses with LOOP receive stripping signal. B Incorrect; stripping signal only goes to bus with loss of voltage and 3A & 3B Pumps will receive start signals. Plausible; need to realize only busses with LOOP receive stripping signal and start goes to 3A & 3B unless racked out. C Correct per above references.

3C ICW Pump on bus with low voltage and 3A & 3B will receive start signals. o Incorrect; 3A and 3B ICW Pumps will receive start signals.

Plausible; need to realize start goes to 3A & 3B unless racked out Cognitive level: 1 Page 130 of 200 06/25/2009 T urkey P o in t IL C 25 N R C Exa m i n a t io n Ques t io n 65 KIA 075K2.03 C ir c ul a ti ng Wa t er Kn ow l e d ge of th e bu s po w er s uppli es t o th e fo ll o win g: E m erge n cy/e ss enti a l SWS pum ps R e f erence: 56 1 0-T-E-1 59 1 s h eet I 5613-T-Ll-1 2, 1 2A, 1 2 B Q u es t io n hi story: EXAM I NER I. J .2 4.54.6.5 Corr e ct answer: C A In correc t; s trippi ng s ign a l o nl y goes to b us w i th l oss o f voltage. Pl aus ibl e; n eed t o r ea li ze o nl y b u sses w ith LOOP r eceive s tri p pi ng s i g n a l. B In co rr ec t; s t ri pping s i gna l o n ly goes t o hus w ith l oss o f vo Jt age and 3A & 38 Pump s w ill r eceive st art signa l s. Pl a u s ibl e; n eed t o rea li ze o nl y bu sses w ith LO OP r eceive st rip p in g s i gna l a nd sta rt goes to JA & 38 u n l ess rac k ed ou t. C Correct p e r a b ove r efe r e n ces. 3C l ew P u mp on b us w ith l ow vo lt age a n d 3A & 38 w ill r ece i ve s t a rt signa l s. o In co rr ect; 3A and 38 l ew Pu mps w ill r ece i ve s t art s ign a l s. P l a u s ibl e; n eed t o r ea l ize s t a rt goes t o 3A & 38 u n l ess ra c k e d o ut Cogn i tiv e l eve l: 1 P ilge 1 30 of 200 Question #66 ES-401 Question 66 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional)

OTSC check required if more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Technical Reference(s):

0-ADM-100 step 5.8.6 04/30/2009 RO 3 G2.1.21 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided)

_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902010 Obi. 3 (As available)

Question Source: Bank # 1.1.23.10.5.3 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 x Que s tion #66 ES-401 Question 66 Written Examination Question Worksheet E xamination Outline C r oss-Reference

Le vel T ier# Group # KIA # Im portance Rating Pr oposed Question: See attached Proposed Answe r: D Explanation (Optio nal): OTSC c h eck required if more than 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s Techn i cal Reference(s

): 0-ADM-100 step 5.8.6 0413012009 RO 3 G2.1.21 6/25 12 009 Form ES-401-5 SRO (Attach if not p r evio u sly provided)-,-

___________

______ _ (including vers i on/revision number) ___________________

_ Proposed refe r ences to be provided to applicants during examination

N one L earning Objective: 6902010 Obi. 3 (As ava i labl e) Question Source: Ba n k # Modified Bank # New 1.1.23.1 0.5.3 --c-(Note changes or attach parent) Question History: L ast NRC Exam (Optional: Questions valida/ed a/ the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the inform ation w ill necessitate a detailed review o( every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamen t a l Knowledge Comprehension o r Analysis 55.41 ---.1Q...

55.43 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exarn.xam Item: 1.1.23.10.5.3 9020100503:

Per 0-ADM-100 Preparation, Revision , Review , Approval and Use of Procedures and Forms, all personel shall verify procedures to be current prior to i nitial use in any activity affecting quality. If the activity continues for more than __ hours , the procedure should be verified ___ _ A) 8) C) D) 12 12 24 24 every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. every 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months thereafter. CORRECT or INCORRECT feedback for item: 1.1.23.10.5.3 ref: 0-ADM-100 step 5.8.6 Item Classification

Undefined Item difficulty

0.00 Keywords: NSO Item weight: 1 Points required for mastery: 1 Correct alternative(s)

C Judging values of alternatives

A=-1 8=-1 C=1 D=-1 Items in G:\Trng\AppsWVEXAMINE\PTN Exam\PTN Exam.xam Item: U.23.1 0.5.3 9020100503

Per Preparation , Revision , Review, Approval and Use of Procedures and Forms, all pers onel shall verify procedures to be current prior to initial use in any activity affecting quality. If the activity continues for more than __ hours , the procedure should be ve r ified ___ _ A) B) C) D) 12 every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. 1 2 every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. 24 every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. 2 4 every 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months thereafter. CORRECT or INCORRECT feedback for item: 1.1.23.10.5.3 ref: O-ADM-1 00 step 5.8.6 Item Classification

Undefined Item difficulty

0.00 Keywords: NSO Item weight: 1 Points required for mastery; 1 Correct alternative(s)

C Judging values of al t ernatives: A=-1 8=*1 C=1 D=-1

0612512009 Turkey Point ILC 25 NRC Examination Question 66

The Turbine Operator (TO) is performing valve lineups in accordance with 3-0P-081.1, Feedwater Heaters, Extraction Steam Vents, and Drains Valve Alignment.

The TO has performed the initial OTSC check for 3-0P-081.1.

Complete the following:

In accordance with 0-ADM-I00, Preparation, Revision, Review, Approval and Use of Procedures, if the valve lineup exceeds (1) hours, the TO is required to perform a second OTSC check by use of (2) (1) (2) A 8 Document Control Hard Copy Index B 8 Lotus Notes C 24 Document Control Hard Copy Index D 24 Lotus Notes Page 131 of 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 66

The Turbine Operator (TO) is performing valve lin eups in accordance with 3-0P* 081.1 , Feedwater H ealers, Extraction Steam Vents, and Drain s Valve Alignment.

The TO has performed the initial OTSC check for 3-0P-OSl.l. Comp l ete th e following:

In accordance with O-ADM-lOO, Preparation , Revision , Review , Approval and Use of Procedures , if the valve lineup exceeds (I) hours, the TO is required to perform a second OTSC check by use of (2) (I) (2) A 8 Document Contro l Hard Copy Ind ex 8 8 Lotus Notes C 24 Document Control Hard Copy Index D 24 Lotu s Notes Pa ge 1 3 1 of200

06/2512009 Turkey Point ILC 25 NRC Examination Question 66 KJA G2.1.21 Ability verify the controlled procedure copy

Reference:

0-ADM-100 5.8.6 OTSC check required if more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Question history: EXAMINER 1.1.23.10.5.3 modified Correct answer: D A Incorrect; correct time is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and use Lotus Notes. Plausible

-bargaining unit shift and Document Control should be able to provide this information B Incorrect; correct time is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Plausible

-bargaining unit shift C Incorrect; use Lotus Notes. Plausible

-Document Control should be able to provide this information D Correct; 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and Lotus Notes Cognitive level: 1 Page 1320[200

06125/2009 Turkey Point IL C 25 NRC Examination Question 66 KIA G2.1.21 Abi lit y ve rif y the co ntr o lled procedure copy

Reference:

O-ADM-IOO 5.8.6 OTSC check req ui red ifmore than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Que s tion hi s tory: EXAMINER 1.1.23.10.5.3 modified Correct answer: 0 A In correct; correct time is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and usc Lotus Notes. Plau s ible -bargaining unit s hift and Document Co ntrol shou ld be able to provide this inf o rmati on B Incorrect; correct time is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Plausible

-bargaining unit shift C Incorrect; u se Lotus Notes. Plausible

-Document Contro l should be able to provide this infonnation D Correct; 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and Lotus Notes Cogni t ive level: 1 Pa ge t]2 of 200 Question #67 ES-401 Question 67 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional)

61hr accumulative and no more than 8 in any hour. Technical Reference(s)

4-NOP-040.02 notes before step 20 RO 3 G2.1.42 6/25/2009 Form ES-401*5 SRO (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective:

6902144 Obi-10 (As available)

Question Source: Bank # Modified Bank # New 1.1.34.44.10.1 ___ (Note changes or attach parent) Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 x *

Quest i o n #67 ES-401 Question 67 Written Examination Question Worksheet Examinati on Outline Cross-

Reference:

Level Tier # G r oup # KIA # Importance Rating Proposed Question: See attached Proposed Answer: A Explanation (Opt ional): 61hr accumulative and no more th an 8 in any h o ur. Technical Reference(s):

4-NOP-040.02 notes before step 20 RO 3 G2.1.4 2 6125120 09 Form ES-401-5 SRO (Att ach if not previously provided)-,-____________

_____ _ (i ncluding ve rsi o n/revisio n number) __________________

_ P roposed references to be provided to applicants during examination

None L earning Objective: 6902144 Ob i. 1 0 (As available) Question Source: Bank # Modified Bank # New 1.1.34.44.10.1 __ ,,-(N ote changes or attach paren t) Question History: Last NRC E xa m (Optional: QUestions validated at the facility since 1at95 will generally undergo less n*go rous review by the NRC; failure to provide the infonnation will necessita te a detailed revie w of e very question.)

Questio n Cognitive Level: 10 C FR Part 55 Content: Comments: Memory or Fundamental Knowledge Co mpr e hension or Analysis 55.41 55.43 10 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.34.44.10

.1 0 021441001

Operators are performing core off-load on Unit 4.

It is 0745 and seven assemblies have been off loaded since 0700.

Spent Fuel Pool (SFP) temperature is 129°F. May the core offload continue?

A) No. The procedural limit on the number of assemblies moved in one hour will be violated.

B) No. The procedural limit of high SFP temperature has been violated. C) Yes. But only one more assembly may be sent over before 0800. D) Yes. But the SFP temperature must be maintained less than 130°F. CORRECT or INCORRECT feedback for item: 1.1.34.44.10.1 RCO Group 19 Audit Exam 4-0P-040.2 steps 4.4 , 4.5 Item Classification

Application Item difficulty

0.50 Keywords:

2.2.28 Item weight: 10 Points required for mastery: 1 alternative(s)

C udging values of alternatives

A=-1 8=-1 C=1 D=-1 Items in G:\Trng\Apps\VVEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.34.44.10.1 02 14 4 1 001; Operato r s are performing core off-l oad on Unit 4.

It is 0745 and seven assemblies have been off loaded since 0700.

Spent Fuel Pool (SFP) temperature is 129°F. May the core offload continue?

A) No. The procedural limit on the number of assemblies moved in one hour wtil be violated. B) No. The procedural limit of h i gh SFP temperature has been violated. C) Yes. But only one more assembly may be sent over before 0800. 0) Yes. But the SFP temperature must be maintained less than 130°F. CORRECT or INCORRECT feedback for [Iem: 1.1.34.44.10.'1 RCO Group 19 Audit Exam 4-0P-040.2 steps 4.4 , 4.5 Itern Classification. AWlicatiurr Item difficulty

0.50 Keywords: 2.2.28 Item weight: 10 Points required for mastery: 1 orrect alternative (s): C udging values of alternat i ves: A=-1 8=-1 C=l 0=-1 06/2512009 Turkey Point ILC 25 NRC Examination Question 67 Operators are performing core off-load on Unit 4.

Core off-load started at 0600.

Three assemblies were moved between 0600 and 0645.

No assemblies were moved between 0645 and 0700.

It is 0745 and seven assemblies have been off-loaded since 0700. In accordance with 4-NOP-040.02 , Refueling Core Shuffle, may the core off-load continue?

A Yes; one more assembly may be sent over before 0800. BYes; two more assemblies may be sent over before 0800. C No; the cumulati v e average fuel transfer rate will be violated.

o No; the number of assemblies moved in one hour will be violated.

Page 133 o f 200

06/25/2009 Turkey Point ILC 25 NRC Examination Question 67 Operators are perfbnning co re off-load on Unit 4.

Core off-load started at 0600.

Three assemblies were m oved between 0600 and 0645.

No assemblies were mo v ed between 0645 a nd 0700.

It is 0745 and seven assemb lie s have been off-load ed si n ce 0700. In accordance w ith 4-NOP-040.02, Refueling CO fe Shuffle, may the core o ff-l oad con tinu e? A Ye s; o n e more assembly may be sent over before 0800. B Yes: two more assemblies ma y be sent over before 0 80 0. C No; the cum ulati ve a ve ra ge fuel tr ansfer rate wi ll be violated.

D No; the number of assemblies mo ve d in onc hour will be vio l ated. Page 1 33 of 200 0612512009 Turkey Point ILC 25 NRC Examination Question 67 KIA 02.1.42 Knowledge of new and spent fuel movement procedures

Reference:

4-NOP-040.02 NOTES before step 20 -6/hr accumulative and no more than 8 in any hour. Question history: EXAMINER 1.1.34.44.10.1

-modified Correct answer: A A Correct lAW 4-NOP-040.02. B Incorrect; only allowed 8 in any hour, so cannot move two. Plausible; this is lAW the 6lhr criteria.

C Incorrect; does not violate the transfer rate. Plausible; moved 10 total for a transfer rate of 5/hr. D Incorrect; allowed to move 8 in an hour. Plausible; already moved 7. Cognitive level: 3 Need to compare number moved with number allowed. Page 134 of 200

06/25/2009 Turkey Point IL C 25 NRC Exam ination Question 67 KIA G2. 1.4 2 Knowledge of n ew and spent fuel movement procedures

Reference:

4*NOp*040.02 NOTES before s tep 20 -6lhr accumu l at ive and no more than 8 in any h our. Question history: EXAMINER 1.1.34.44.10.1 -modified Correct answer: A A Co rre ct l AW 4-NOP-040.02.

B In correct; only allowe d 8 in any h o ur , so cannot m ove two. Pl a u s ible; this i s lAW the 6 t hr cri t e ri a. C In correct; does n O I vio l a t e th e tr ansfer rate. Plau sib l e; moved 10 total for a transfer rate of 5/hr. D In correct; a ll owed to m ove 8 in an hour. Plausible; already moved 7. Cogn iti ve le vel: 3 Need 10 compare number moved with numb er allowed . Page 134 of200 Question #68 ES-401 Question 68 Written Examination Question Worksheet Examination Outline Gross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: B Explanation (Optional)

RO 3 G2.2.11 6/25/2009 Form ES-401-5 SRO Step 4.13.5.1 lists lifted leads as requiring TSA. Step 5.1.1 lists the exceptions to TSA. 5.1.1.5 exempts tripping 8/S. 5.1.1.4.c exempts hose drains & power cords Technical Reference(s):

0-ADM-503 steps 4.13.5 & 5.1.1 04/27/2009 (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective:

6902029 Obi. 4 (As available)

Question Source: Bank# 1.1.23.29.3.3 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 x Que s ti o n #68 ES-401 Question 68 Written Examination Question Worksheet Examination Outline Gross-Refe ren ce: Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: B Explanation (O ptional): RO 3 G2.2.11 6/25/2009 Form ES-401-5 SRO S tep 4.1 3.5 , 1 li sts lift e d l ea d s as r eq uirin g TS A. S t e p 5.1.1 li s t s th e exceptions t o TSA. 5.1.1.5 exe mpt s trippin g B/S. 5.1.1.4.c exempts h ose drains & power co rd s Te c hnical Reference(s)

0-AOM-503 steps 4.13.5 & 5.1.1 04/2 712 009 (A ttach if not previously pro vi ded)-,-_________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 690 2 029 Obj. 4 (As available) Question Source: Bank# Mod i fied Bank # New 1.1.23.29.3.3 __ ::-(Note changes or attach parent) Question History: Last NRC Exam (Op t ional: Ques t ions valida te d at the fa cili fy since 1 0/95 will generally undergo less rigorous review by the NRC; f ailure to provide the infonnation will necessitate a detailed review of eve/}' question.)

Question Cognit iv e Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Ana l ysis 55.41 55.43 10 x Items in G:\Trng\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.23.29.3.3 020290303; Per 0-ADM-503, Control and Use of Temporary System Alterations

Which ONE of the following conditions requires a Temporary System Alteration (TSA) for configuration control? A) Hose installed to direct flow from dra i n lines to a floor drain. 8) Temporary removal of motor heater fuses under an ECO. C) Temporary electrical equipment connected to existing receptacles. D) Lifting leads on a faulty component to allow continued safe plant operation.

CORRECT or INCORRECT feedback for item: 1.1.23.29.3.3

REFERENCE:

ADM-503 4.1 Item Classification

Knowledge Item difficulty

0.50 Keywords: RCO, 2.2.11 I tem weight: 10 Points required for mastery: 1 Correct alternat i ve(s): D Judging values of alternatives

A=-1 8=-1 C=-1 D=1 emo Field: DL: 300 NAnna 1993 NRC RO e x am Items in G:\T rn g\.Apps\WEXAMI N E\P TN Exam\PTN Exam.xam Item: 1.1.23.29.3.3 020290303; Per Control and U se of T emporary System A lt erations: VlJhich ON E of the following co nd itions r equires a T emporary System Alteratio n (T SA) fo r configuration con tr o l? A) H ose installed to direct flow fr om drain tines to a floor drain. B) T emporary removal of motor heater f uses under an ECO. C) Temporary electrical equipment connected to exist i ng receptac le s. 0) Lifting l eads on a f aulty component to allow co nt inued safe p l an t operation. CORRECT or IN C ORRECT feedback f o r item: 1.1.23.29.3.3

REFERENCE:

AD M-5034.1 lIem Classification

Knowledge Item difficul ty: 0.50 Keywords: RCO , 2.2. t t Item weight: 1 0 Points requ i red for mastery: 1 Correct alternative(s)

D Judging values of alternatives

A=-1 8=-1 C=-l 0=1 Memo Fie l d: DL: 3 00

NAnna 1993 NRC RO exam 06/25/2009 Turkey Point ILC 25 NRC Examination Question 68 In accordance with 0-ADM-503, Temporary System Alteration, which one of the following requires a Temporary System Alteration (TSA) for configuration control? A Hose installed to direct flow from a drain line to a floor drain B Installing temporary ventilation in the 4B MCC Room to maintain its temperature below design limits. C A temporary electrical heater plugged into a 120V outlet to maintain the Unit 3 Charging Pump Room above 65°F. D Tripping bistables in accordance with 3/4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels Page 135 of 200

06/25/2009 Turkey Point ILC 25 NRC Examination Question 68 I n accordance with O-ADM-503, Temporary System A l teration, whic h one of the follow i ng requi r es a Temporary System Alteration (TSA) for configuration control? A Ho s e installed to direct flow from a drain line to a floor drain B Installing temporary ventilation in the 48 MeC Room to maintain its temperature below design limit s. C A temporary electrical heater plugged into a l20V outlet to maintain the Unit 3 Charging Pump Room above 65°F. o Tripping bistables in accordance with 3/4-0NOP-049.1, Deviation or Failure of Safety Re l ated or Reactor Protection Channels Pa ge 13 5 o f 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 68 KIA G2.2.11 Knowledge of the process for controlling temporary design changes

Reference:

0-ADM-503 sections 4.13.5, & 5.1.1 Step 5.1.1 lists the exceptions to TSA. 5.1.1.5 exempts tripping B/S 5.1.1.4.c exempts hose drains & power cords Question history: EXAMINER 1.1.23.29.3.3 modified Correct answer: B A Incorrect lAW above reference. Plausible; temporary change to system B Correct lAW above reference C Incorrect IA W above reference.

Plausible; need to realize use of existing 120V outlets does not require TSA o Incorrect lAW above reference.

Plausible; temporary change to system Cognitive level: 1 Pag e 136 of 200

06/25/2009 Turkey P oi nt IL C 25 NRC Examination Quest i o n 68 KIA G2.2.11 Knowledge of the process for co ntr o lli ng temp o r ary design c h a n ges R efe r e n ce: O-ADM-503 sections 4.13.5, & 5.1.1 Step 5.1.1 li sts the exce pti ons t o TSA. 5.1.1.5 exemp t s tri p pin g B/S 5.1.1.4.c exe mpt s h ose dr a in s & power cor d s Question history: EXAM I NER 1.1.23.29.3.3 modified Correct a n swer: B A In co rr ec t l AW above reference.

P l ausib l e; t emporary c han ge to system B Correc l l AW , lh ove r efe r e n ce C In correct l AW above r efe r ence. Pl a u si bl e; n eed to r ea li ze use of ex i st ing 1 20V o utlet s d oes n ot require TSA o In co rr ect fA W above reference.

Plausible; temporary c h ange to system Cogni ti ve l eve l: 1 Page \36 of2oo Question #69 ES-401 Question 69 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional)

RO 3 G2.2.4 6/25/2009 Form ES-401-5 SRO Technical Reference(s):

3-0NOP-003

.B step 4 & cautions & notes 06/27/200B (Attach if not previously provided)4-0NOP

-003.B step 4 & notes 06/27/200B (including versionlrevision number)3-0NOP-003

.9 caution before step 5 04/27/2009 4-0NOP-003.9 caution before step 5 06/27/200B Proposed references to be provided to applicants during examination:

None Learning Objective: 6902111A Obi. 6 (As available)

Question Source: Bank # Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation w i ll necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X Quest i on #69 ES-401 Question 69 Written Examination Question Worksheet Examination Outline Cross-Refe rence: Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: A Explanation (Optional)

RO 3 G2.2.4 6/25 12 009 Form ES-401-5 SRO Technical Reference(s)

3-0NOP-003

.8 step 4 & cautions & notes 06/27/2008 (Attach if not previously provided)4-0NOP

-003.8 step 4 & notes 06/27/2008 (including version/revision number)3-0NOP-003.9 caution before step 504/2712009 4-0NOP-003

.9 caution before step 5 06/27/2008 Proposed references to be provided to applicants during examination:

None Learning Objective: 6902111A Obi. 6 (As available)

Question Source: Bank # Modified Bank # New __ ,,-(Note changes or attach parent) X Question H istory: Last NRC Exam (Optional: Queslions validated al the fac ili ty since 10195 will generally undergo less n*gorous review b y the NRC; failu re t o provide the in format ion will necessita t e a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 7 X 06125/2009 Turkey Point ILC 25 NRC Examination Question 69 Units 3 and 4 have both simultaneously lost 120V Panel P08. How will the Feed Regulating Valves (FRVs) respond on each unit? Unit 3 Unit 4 A A S/G Lock up Auto B S/G Auto Auto C S/G Manual Manual B AS/G Auto Lock up B S/G Auto Auto C S/G Manual Manual C A S/G Auto Lock up B S/G Lock up Lock up C S/G Auto Lock up D AS/G Lock up Auto B S/G Lock up Lock up C S/G Lock up Auto Page 1370[200 06/25/2 009 Turkey Point IL C 25 NRC Exa mination Question 69 Un its 3 and 4 have both s imult a neou sly l ost 120V Pan e l P0 8. How wi ll the Feed Regulating Val v es (FRVs) respond on each unit? Unit 3 Unit 4 A A S/G Lock up Auto B S/G Auto Auto C S/G Manual Manual B A S/G Auto L oc k up B S/G Auto Auto C S/G Manual Manua l C A S/G Auto Lock up B S/G Lock up L ock up CS/G Auto Lock up o AS/G Lock up Auto B S/G Lock up Lock up CS/G Lock up Auto Pa ge 137 of200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 69 KJA G2.2.4 (multi-unit)

Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

Reference:

3-0NOP-003.S CAUTIONS & NOTE before step 4 4-0NOP-003.S NOTEs before step 4 3-0NOP-003.9 CAUTION before step 5 4-0NOP-003.9 CAUTION before step 5 Question history: New Correct answer: A A Correct per above references B Incorrect per above references.

Plausible; this is 3P09 and 4POS. C Incorrect per above references.

Plausible; this is 3P09 and 4P09. o Incorrect per above references. Plausible; this is 3POS and 4P09. Cognitive level: 1 Page 138 of 200 06/25/2009 Turkey P o int IL C 25 N R C Examination Question 69 KIA 02.2.4 (multi-unit)

A bilit y to explain the va ri a ti o n s in con trol b oar d la yo ut s, sys tem s, in st rumen tatio n a nd procedural actions between unit s at a fac ilit y.

Reference:

3-0NO P-0 03.8 CAU TIO NS & NOTE b efore step 4 4-0NOP-003

.8 NO T Es b e f o re s tep 4 3-0 NO P-0 03.9 CAUT IO N b efore ste p 5 4-0NOP-003

.9 CAUT IO N b efo re s tep 5 Question hi s t ory: New Correct answer: A A Correct per above r efe ren ces B In correct p e r above r e f e r e n ces. Pl a u s ib l e; thi s is 3 P 09 and 4P0 8. C In correct p er a b ove references. Plausible; thi s is 3 P 0 9 and 4P0 9. D In co rr ect p er above ref e r e n ces. Plausib l e; this is 3 P08 a nd 4P09. Cogn iti ve le ve l: I P ag e 138 o f200 Question #70 ES-401 Question 70 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional)

RO 3 G2.2.44 Technical Reference(s):

4-NOP-041.04 section 4.2 12/09/2008 (Attach if not previously provided) 4-ARP-097.CR A 311 03/20/2009 (including version/revision number) 5610-T -D-16A 04/29/2009 Proposed references to be provided to applicants during examination:

None Learning Objective: 6902409 Obi-6.9 (As available)

Question Source: Bank# 6/25/2009 Form ES-401-5 SRO 4.4 Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Robin so n ex am Jun e, 2 00 7 Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 5 X Que s ti on #7 0 ES-401 Question 70 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answe r: o Explanalion (Oplional): RO 3 G2.2.44 Technical Reference (s): 4-NOP-041.04 sec tion 4.2 12/09/2008 (A ttach if not previously provided) 4-ARP-097.CR A 311 03/20/2009 (i ncluding version/re vision number) 561 O-T -O-16A 04/29/2009 Proposed references to be provided to applicants during examination

None Learning Objective: 6902409 Ob i. 6.g (As available) Ques tion Sou r ce: Bank # 6/2512009 Form ES-401-5 SRO 4.4 M odi f ied Bank # ==,,---(Note changes or attach parent) New X Question H istory: Last NRC Exam (Optional: Questions validated at t he facility since 10195 will generally undergo less rigorous review by t he NRC; failure to provide the information will necessi t ate a detailed review of every question.) Questi o n Cognitive Level: 10 CFR Part 55 Content: Comments: R o bin so n exa m June, 2007 Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _5_ 55.43 X 06125/2009 Turkey Point ILC 25 NRC Examination Question 70

A plant cool down is in progress on Unit 4.

RCS temperature is 290°F and lowering.

RCS pressure is 370 psig and lowering.

Shortly after the OMS switches are placed in LO PRESS OPS the following alarm is received:

).> A 311, OMS LO PRESS OPERATION Which one of the following is the cause of the above alarm? A PORV-4-456 is open B RCS pressure is too high to place OMS in service C RCS temperature is too high to place OMS in service D MOV-4-535, PORV Block Valve, is de-energized Page 1390[200 06/25/2009 Turkey P o int lLC 25 NRC Examination Question 7 0

A plant cooldown is in progress o n U ni t 4.

R eS t em peratur e i s 290°F and l oweri ng.

R eS pr ess ure i s 370 p s ig a nd l owering.

S h o rtl y after th e OMS sw it ches are pl ac ed in LO PR ESS OPS the followi ng a l ann is r ece i ved: p A 3/1. OMS LO PRESS OPERAT I ON W hi c h o n e of th e foll ow ing i s the ca u se o f the abov e alann? A POR V-4-4 56 i s open B R eS pressure i s 1 00 hi g h to pl ace OMS in service C R eS t e mper at ur e i s to o high to place OMS in serv i ce D MOV-4-535 , PORV Bl ock Va l ve, i s d e-e n e rgi ze d Pa ge 1 39 or 200 06125/2009 Turkey Point ILC 25 NRC Examination Question 70 KIA 02.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions

Reference:

4-NOP-041.04 section 4.2 4-ARP-097.CR A 311 561O-T-D-16A Question history: Robinson exam June, 2007 Correct answer: D A Incorrect; PORV open doesn't cause this alarm. Plausible; OMS opens PORV and PORV switch in close position will actuate this alarm B Incorrect; pressure input to this alarm is less than 360 psig. Plausible; above the 360 psig setpoint.

C Incorrect; temperature not input to this alarm. Procedure requirement for placing OMS in service at 300°F. D Correct; pressure going below 360# and PORV block breaker not closed will cause this alarm. Cognitive level: 2 Need to compare conditions to what will actuate alarm. Page 1400[200 *

06 1 25 1 2009 Turkey Point IL C 25 NRC Examination Question 70 KiA G2.2.44 Abi lit y t o interpret contro l room indications to verify the s tatu s an d o perati on of a system , and understand how operator actions and directives affect plant and sys tem co nditi o n s

Reference:

4-NOP-041.04 section 4.2 4-ARP-09 7.CR A 3 1 1 5610-T-D-1 6A Question hi story: Robinson exam June , 2007 Correct answer: D A Incorr ect; PORVopen doesn't cause this alann. Plausible; OMS opens PORVand POR V sw it ch in close p osit i on will actuate thi s alarm B In correct; pre ss ure input to thi s alarm i s less than 360 psig. Pl aus ibl e; above the 360 psig selpoint.

C In correct; temperature nOI input to this alarm. Procedure requirement for placing OMS in service at 300 o P. D Correct; pressure going below 360# a nd PORV block breaker not closed wi ll ca u se this alarm. COf,'l1itive l eve l: 2 Need to compare co nditi ons to what w ill actuate alarm . Pag e 140 0000 Question #71 ES-401 Question 71 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: C Explanation (Optional):

RO 3 G2.3.11 6/25/2009 Form ES-401*5 SRO R-IS is set in Control Room by RO. RCV-OIS is not adjusted for flow -flow adjustment by Valve 1269 Technical Reference(s):

.::::.0-....::O::.!P_-..:;::.0.;::..6.!..:1

.-!..1

__________

_ (Attach if not previously provided) 5610-M-3061 sheet 406/01/2007 (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902149 Obi. 10 (As available)

Question Source: Bank# 1.1.24.49.4

.1 Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _11_ 55.43 x Question #7 1 ES-401 Question 71 WriHen Examination Question Worksheet Examination Outline Cross*Reference

Level Tier # Group # KIA # Imp ortance Rating Proposed Question:

See attached Proposed Answer: C E x planation (O ptional): RO 3 G2.3.11 6/25/2 009 Form ES-401-5 SRO R*1 8 i s se t in Co ntrol Room by R O. RCY*018 i s not ad ju s t ed for flo w* flo w adjustment by Valve 1 2 69 Te c hnical Reference (s):

_____ _ (A ttach i f not prev io usly p r ovided) 5610-M-3061 sheet 4 06/01/2007 (including v e rsio n/rev ision number) ___________________

_ P r oposed referen ces to be pro vi ded to applicants during examination

None Learning Objective: 6902149 Obi. 10 (As available)

Question Source: Bank # Modified Bank # New 1.1.24.49.4.1

==:7""" (Note changes o r attach parent) Question History: Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; fai/ure to provide the information will necessi t ate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Co ntent: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _1_1_ 55.43 x Items in G:\Tmg\Apps\WEXAMINE\PTN Exam\PTN Exam.xam Item: 1.1.24.49.4.1 9021490401 A Waste Monitor Tank is to be released.

Which one of the following correctly states how PRMS-R-18 will be set and how the flow rate will be established?

A) The SNPO will set the High and Warning values for PRMS-R-18. The SNPO will locally adjust the flow rate using a manual throttle valve. 8) The SNPO will set the High and Warning values for PRMS-R-18. RCV-018 , Liquid Waste Discharge Valve , will control the flow rate at a value set by the SNPO. C) The RCO will set the High and Warning values for PRMS-R-18. The SNPO will locally adjust the flow rate using a manual throttle valve. 0) The RCO will set the High and Warning values for PRMS-R-18.

RCV-018 , Liquid Waste Discharge Valve , will control the flow rate at a value set by the SNPO. CORRECT or INCORRECT feedback for item: 1.1.24.49.4.1 0-op-061 .11 Item Classification:

Knowledge Item difficulty

0.00 Keywords: 068 A4.02 Item weight: 10 Points required for mastery: 1 orrect alternative (s): C udging values of alternat i ves: A=-1 8=-1 C=1 0=-1 Items in G:\TmglApps\VVEXAM1NE\PTN Exam\PTN Exam.xam It em: 1.1.2 4.49.4.1 9021490401 A Waste Monitor Tank is to be released. \tVhich one of the following correctly states h o w PRMS*R*18 will be set and how the flow rate will be established?

A) The SNPO will set the High and Warning values for PRMS*R*18. The SNPO will locally adjust the fl ow rate using a manual throttle valve. S) The SNPO will set the High and Warning va lues for PRMS-R-18. RCV-01 B , Liqu i d Waste Dis cha rge Valve , will co nt rol the fl ow rate at a value set b y the SNPO. C) The RCa will set the High and Warning values f Of PRMS-R-1 B. The SNPO wililocaUy adjust the flow rate using a manual throttle valve. D) The RCa will set the Hig h and Warning values for PRM S-R-1S. R CV*0 1B , Liqu i d Waste Discharge Valve , will cont rol the fl ow rate at a value set b y the S NPO. CORRECT o r INCORRECT f eedbac k for item: 1.1.2 4.49.4.1 O-op-061.11 1Iem Classificatio n: Knowledge Item difficulty

0.00 Keywords:

068 A4.02 Ilem weig ht: 1 0 Poin ts required for mastery: 1 alternative(s

): C values of alternativ e s: A=-l 8=-1 C=1 0=-1 06125/2009 Turkey Point ILC 25 NRC Examination Question 71 A Waste Monitor Tank is to be released.

In accordance with 0-OP-06l.ll, Waste Disposal System Controlled Radiological Liquid Release, how will PRMS-R-18, Waste Disposal Liquid Effluent Monitor, be set and how will the flow rate be established?

A The SNPO will locally set the High and Warning values for PRMS-R-18.

The SNPO will locally adjust he flow rate using a manual throttle valve. B The SNPO will locally set the High and Warning values for PRMS-R-18. RCV-018, Liquid Waste Discharge Valve, will control the flow rate at a value set by the SNPO. C The RCO will set the High and Warning values for PRMS-R-18.

The SNPO will locally adjust the flow rate using a manual throttle valve. D The RCO will set the High and Warning values for PRMS-R-18.

RCV -018, Liquid Waste Discharge Valve, will control the flow rate at a value set by the SNPO. Page 141 of200 06/25/2009 Turkey P o int IL C 25 NRC Exa mi nat i on Question 7 1 A Waste Monitor Tank is to be released. (n accordance w ith O-O P-06 I. I I , Waste Di sposa l System Con t ro lled Rad io l ogic al Liquid Release, how w ill PR MS-R-1 8 , Waste Disposal Liquid Effluent Monitor , be set and h ow wi ll the flow rat e be estab li shed? A The SNPO will locally sc i the High and Warn in g va lu es f or PRMS-R-J 8. The SNPO w ill locally adj u s t he flow r ate u s ing a manu a l thr o ttl e va l ve. B T h e SN PO w ill l oca ll y se l the H igh and Warn in g values for PRMS-R-IS. ReV-OIS, Liquid Waste Discharge Valve , w ill contro l the fl ow rate a t a va lu e sct b y Ih e SN P O. C T h e RCO w ill se l the Hi g h a nd Warning values for PRMS-R-1 8. The SNPO wi ll l oca ll y adjusllhe flow rale u s ing a manuallhroll i e va l ve. o The RCO w ill se t t h e Hi g h a nd Warn in g va lu es for PRMS-R-1 8. ReV-DI8, Liquid Waste Discharge Va l ve , wil l con t ro l th e fl ow r ate a t a val u e se t by Ihe SNPO. Pa g e 141 0 1'20 0 06125/2009 Turkey Point ILC 25 NRC Examination Question 71 KJAG2.3.11 Ability to control radiation releases

Reference:

0-OP-061.11 5610-M-3061 sheet 4 R-18 is set in Control Room by RO. RCV -018 is not adjusted for flow -flow adjustment by Valve 1269 Question history: EXAMINER 1.1.24.49.4.1 Correct answer: C A Incorrect; R-18 set by RO. Plausible; RCV -018 is controlled from WBP B Incorrect; R-18 set by RO and flow set by manual valve. Plausible; RCV -018 is controlled from WBP and RCV-018 will stop flow. C Correct; RCO sets R-18 and flow by manual valve o Incorrect; flow set by manual valve. Plausible; RCV-OI8 will stop flow Cognitive level: 1 Page 1420[200 06/25/200 9 Turkey Point ILC 25 NRC Examinat i o n Qu es ti o n 7 1 KIA G2.3.11 A bilit y t o control radiati o n relea ses Referen ce: 0-OP-061.11 56 10-M-3 061 s h eet 4 R*1 8 is set in Co ntrol Room b y RD. R eV -01 8 i s not adjusted for fl ow -fl ow adjustment by Va l ve 1 26 9 Question hi story: EXAM I NE R 1.1.24.49.4

.1 Correct answer: C A in co rrect; R-1 8 set b y RD. Pl a u s ible; R ev -01 8 i s c o ntrolled from WBP B In co rrect: R-1 8 se t by RO and now se t by manual valve. Plau s ible: R eV-OI8 is co ntr o lled from WBP and R eV-O I S will stop fl ow. C Co rre c t; R CO se t s R-1 8 and flo w b y manual valve D In correct; fl ow sel b y manual va l ve. Plau s ible; R eV-OI S will s top flow Cogn iti ve le ve l: I Page 142 of 200 Question #72 ES-401 Question 72 Written Examination Question Worksheet Examination Outline Cross-Reference

Level Tier # Group # KIA # Importance Rating Proposed Question:

See attached Proposed Answer: A Explanation (Optional)

RO 3 G2.3.13 Technical Reference(s):

0-ADM-600 5.1.1.1/5.1

.1.2/Att 1 08/21/2008 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided).

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902970 Obi. 14 (As available)

Question Source: Bank # See comment Modified Bank # ___ (Note changes or attach parent) New Question History: Last NRC Exam (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infonnation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 --1L 55.43 PTN SRO 22 Audit examination question #1 x Question #72 ES-401 Question 72 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question: See attached Proposed Answer: A Explanation (Optional)

RO 3 G2.3.13 Technical Reference(s)

0-ADM-600 5.1.1.1/5.1.1.21Att 1 08/21/2008 6/25/2009 Form ES-401-5 S RO (Attach if not previously

_________________

_ (including version/revision number)' ____________________

_ Proposed references to be provided to applicants during examination

None Learning Objeclive: 6902970 Obi. 14 (As available)

Question Source: Bank# See commen t Modified Bank # __ (Note changes or attach parenl) New Question History: Last NRC Exam (Optional: Questions validated a t the facility since 10/95 will generally undergo less rigorous review by the NRC; failure 10 provide fhe infonnafion w ill necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Conlent: Comments: Memory or Fundamenta l Knowledge Comprehe nsi on or Analysis 55.41 ---.1L 55.43 PTN SRO 22 Audit examinatjon que s tion # 1 x

.' I . '. _.: I' ;, '. QUESTION 1 Which one of the following would maintain station exposure as low as reasonably achievable and comply with station admin requirements?

The general area dose rate is 100 mremlhr. A. A qualified worker who has previously performed this task and can complete the job in 20 minutes. This worker has received 800 mrem of exposure this year. B. A qualified worker who has previously performed this task and can complete the , job in 30 minutes. This worker has received 500 mrem of exposure this year. C. A team of a female worker who is qualified to perform the task and a male worker who needs to qualify to this task. The female is a declared pregnant worker. The team will need 15 minutes to complete the task. The female has no dose and the male worker has 200 mrem for the year .* D. A team of a male and female both are qu-a lified to perform the task but will take '_.-.1' 20 minutes to complete the task. The female is NOT a declared pregnant worker. Each has less than] 00 mrem this year. -"-"; \'.

ANSWER: A fm i T,i:J1;"'_" ',J; ,.;. ' J T:-: , ,-,' -7 r-;::;p ;:;NCE' .. '" -'-' ).. . ;; (: x: ' X'jA: 2.3.2 lhf HIST-ORY: Ed Roberts bank :(. , '-.':' . -": " *

QUESTION I Which one of the following wo uld maint a in s tati on exposure as low as r easo nabl y achiev able a nd comp l y wi th sta tion adrnin r eq uir e m e nts?

The general area do se r a te is 100 mremlhr. A. A qual ified worker who ha s pr ev i o u s l y perfonned tlu s ta s k and c an complete th e job in 20 minutes. Thi s worker ha s r ece i ved 800 mr e m of expos u re thi s year. B. A qualified worker w h o h as previously p e rf onne d this task and ca n com pl ete th e job i n 30 minute s. Thi s worker ha s r ece iv ed 50 0 mrem of exposure th is yea r. C. A t eam ofa f e m a l e worke r w h o is qu a lifi ed to perform th e ta s k and a m a le worker who needs to qu a li fy t o this task. Th e female is a declared pr egnan t worker. Th e team w ill need 15 minute s to co mpl e te the task. The female ha s n o dose and the male worker h as 200 mrem for the yea r . D. A t e am ofa male and female both a re qli'alified t o perfonn th e task but will take 20 minutes to com ple te the tas k. The i s NO T a declared p r egnant worker. Each h as l ess than 100 mrem thi s year ... <,. , I .' ' , " }V A: 2.3.2 -i i .,. HI STORY: E d Roberts bank .f 06125/2009 Turkey Point ILC 25 NRC Examination Question 72

An OSP is to be performed in the Auxiliary Building.

The general area dose rate is 100 mremlhr. In accordance with 0-ADM-600, Radiation Protection Manual, which one of the following will maintain station exposure as low as reasonably achievable and comply with station administrative requirements? A A qualified worker who has previously performed this task and can complete the job in 20 minutes. This worker has received 800 mrem of exposure this year. B A qualified worker who has previously performed this task and can complete the job in 30 minutes. This worker has received 500 mrem of exposure this year. C A team of a male and a female worker, both qualified to perform the task. The female is NOT a declared pregnant worker. The team will need 20 minutes to complete the task. Each worker has less than 100 mrem this year. D A team of a female worker who is qualified to perform the task and a male worker who needs to qualify to this task. The female is a declared pregnant worker. The team will need 15 minutes to complete the task. The female has no dose and the male worker has 200 mrem for the year. Page 1430f200 06125/2009 Turkey Point lLC 25 NRC Examination Question 72

An OSP is to be perfonned in the Auxi li ary Building.

The genera l area dose rate is 100 mremlhr. In acco rd ance with Radiation Protection Manual, which one of the following will maintain statio n exposure as l ow as reasonably achievab l e and comply with s tation administrati v e requirements

? A A qualified worker who has previously perfonned this task and can comp l ete the job in 20 minutes. This worker has received 800 mrem of exposure this year. B A qua l ified worker who has previously perfonned thi s task and can comp l ete the job in 30 minutes. This worker ha s received 500 mrcm of exposure this year. C A team ofa male and a female worker , both qualified to perfonn the task. The female is NOT a declared pregnant worker. The team will need 20 minutes to comp l ete the task. Each worker has l ess than tOO mrem this year. o A team of a female worker who is qualified to perfonn the task and a male worker who needs to qualify to this task. The female is a declared pregnant worker. The team w ill need 15 minutes t o comp l ete the task. The female has no dose and the male worker has 200 mrem for the year. Pag e 143 o r2 00 06/25/2009 Turkey Point ILC 25 NRC Examination Question 72 KIA 02.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties

Reference:

0-ADM-600 steps 5.1.1.1, 5.1.1.2, and Attachment 1 Question history: PTN SRO 22 Audit examination question #1 Correct answer: A A Correct; this scenario has least total dose. B Incorrect; more dose than A. Plausible; worker's accumulated dose is less C Incorrect; more dose than A. Plausible; worker's accumulated dose is less -common misconception is that worker's accumulated dose counts more than site accumulated dose. C Incorrect; more dose than A. Plausible; worker's accumulated dose is less -common misconception is that worker's accumulated dose counts more than site accumulated dose. Cognitive level: 3 Need to apply ALARA and calculate doses Page 144 of 200

06/25/2 0 09 Turkey P oint ILC 25 NRC Examina ti on Ques t ion 72 KIA G2.3.1 3 Know l edge of radiological safe t y procedure s pertaining t o licensed operator dutie s R eference:

0-A D M-600 Sleps 5.1.1.1. 5.1.1.2. and Attachment I Q u estio n hi story: P TN SRO 22 Audit examination que s ti o n #1 Correct answer: A A Correct; thi s sce nario h as l east total dose. B In co rrect; m o r e do se tha n A. Plausible; wo r ker's accu mul ated d ose is l ess C I ncorrect; more do se th an A. Plausible; worker's accumulated d ose i s l ess -co mm o n mi sco nception i s th at wo rk er's accu mul ated dose co unt s more than s ite accu mul ate d dose. C Incorrect; more dose than A Pl a u s ible; wo rk e r's acc umulat e d dose i s le ss -common misconception i s thai wor ker's acc umul ated dose counts more than s ite acc umul a te d do se. Cogni t ive le ve l: 3 Nee d to app l y ALARA a nd calcu l ate doses Page \44 of 200 Question #73 ES-401 Question 73 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: D Explanation (Optional):

2/4 channels above 108% is RPS trips setpoint Technical Reference(s)

5610-T-L 1 sheet 2 10/31/00 RO 3 G2.4.2 6/25/2009 Form ES-401-5 SRO (Attach if not previously provided)

________________

_ (including version/revision number) _________________

_ Proposed references to be provided to applicants during examination:

None Learning Objective: 6902204 Obi-6 (As available)

Question Source: Bank # Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional:

Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X Questio n #73 ES-401 Question 73 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier# Group # KiA # Importance Rating Proposed Question: See attached Proposed Answe r: D Explanation (Op ti onal): 2/4 channels above 108% i s RPS trip s sctpoint Technical Reference(s)

5610-T-L 1 sheet 210/31/00 RO 3 G2.4.2 6125/2009 Form ES-401-5 SRO (Attach if not previously provided):;-

_____________

__ _ (inc luding versio n/revision number) __________________

_ Proposed references to be provided to applicants during examination:

N one Learning Objective: 6902204 Obi. 6 (As available)

Question Source: Ban k# Modified Bank # New ==;;-(Note changes or attach parent) X Question Hi story: Las t NRC Exam (Optional: Questions valida ted at ihe facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Lev el: 1 0 CFR Part 55 Content: Comments: Me mory or Fundamental Knowledge Comprehension or Analysis 55.41 _7_ 55.43 X 06125/2009 Turkey Point ILC 25 NRC Examination Question 73

A steam leak has occurred on Unit 4

The power range nuclear instruments indicate the following: N-41 109.0% N-42 107.0% N-43 108.5% N-44 106.0% Which of the following is correct? A Reduce turbine load to restore the unit to 100% power. B Insert control rods to restore the unit to 100% power. CEnter 4-0NOP-l 00, Fast Load Reduction, and commence load reduction.

D Trip the reactor and enter 4-EOP-E-0, Reactor Trip or Safety Injection.

Page 145 of 200 06 1 25 1 2009 Turkey P oi nt ILC 25 NRC Exam in ation Que s tion 73

A steam leak has occurred on Unit 4

The power range nuclear instruments indicate the following: N-41 1 09.0% N-42 1 07.0% N-43 108.5% N-44 106.0% Whic h of the following is correct? A Reduce turbine l oad to r estore the unit to 100% power. B In sert control rods to restore the unit to 100% power. CEnter 4-0NOP-l 00 , Fast Load Reduction , and commence load reduction.

o Trip the reactor and en t er 4-EOP-E-O, Reactor Trip or Safety Inje ction. Pa ge 145 of200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 73 KJA 02.4.2 Knowledge of system setpoints, interlocks and automatic actions associated with EOP entry conditions

Reference:

5610-T-Ll sheet 2 2/4 channels above 108% is RPS trips setpoint Question history: New Correct answer: D A Incorrect; 2/4 channels above 108%. Plausible; average is less than 108% and would reduce to less than 100%. B Incorrect; 2/4 channels above 108%. Plausible; average is less than 108% and would reduce to less than 100%. C Incorrect; 2/4 channels above 108%. Plausible; average is less than 108% and would reduce to less than 100%. D Correct per above reference Cognitive level: 1 Page 146 of 200 06/25/2 0 09 Turk ey P o int lLC 2 5 N R C Exa min a ti on Q u es ti on 7 3 KIA G 2.4.2 Kn ow l e d ge of sys t e m se tp o in ts, int e rl oc k s and automat i c ac ti o n s assoc i a t e d w ith EO r e ntr y co nditi ons Re f e r ence: 56 10-T-L I s h ee t 2 2/4 c h a nn e l s a b ove 1 08% i s RP S trip s se tp o int Ques ti o n hi s t ory: New C orrect answer: D A I n correc t; 2/4 c h a nnels a b ove 1 08%. Pl a u si bl e; ave ra ge i s le ss th an 1 08% a nd wo u l d r e du ce t o le ss th an 1 0 0%. B I n co rr ect; 2/4 c h a nn e ls a b ove 10 8%. Pl a u s ibl e; av er age i s l ess th an 1 08% a nd wo uld r e du ce t o l ess th an 1 00%. C I n correc t; 2/4 c h an n e l s above 1 08%. Plau si bl e; a ve ra ge i s l ess th a n 1 08% a nd wo ul d r e du ce t o l ess th a n 10 0%. o Co rr ect p er a bove r e f ere n ce Cogn iti ve l eve l: I Page 1 46 of 200 Question #74 ES-401 Question 74 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KIA # Importance Rating Proposed Question: See attached Proposed Answer: o Explanation (Optional):

All alarms would come in on N-44 failure. RO 3 G2.4.45 6/2 5/2009 Form ES-401*5 SRO Technical Reference( s):

_________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination

None Learning Objective: 6902253 Obi. 4 (As available)

Question Source: Bank # Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to prov i de the information will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X Question #7 4 ES-401 Question 74 Written Examination Question Worksheet E x amination Outline Cross-Refe renc e: Level Tier # Group # KiA # Importance Rating Proposed Question: See attached Proposed Answe r: D Explanation (Optional)

A ll a lann s wo uld co m e in on N-44 failure. RO _3_ G2.4.45 6 12512 009 Form ES-401-5 SRO Technical Reference (s): '!:3c>-O;CN"O""P::>-0"'5"'9".SL.!.11!L'.c14,,'

... 2"'00"'7'-

_________ _ (A ttach jf not previously provided)-,--_________________

_ (includ ing v ersion/revisio n number) ____________________

_ Proposed referen c es to be provided to applicants during examination

None Learning Objective:

6902253 Obi. 4 (A s available) Question Source: Bank# Modified Bank # New __ ,,--(Note changes or attach parent) X Ques t ion Hist ory: L ast NRC E x am (Optional: Quest io ns validated at Ihe facility since 10195 will generally undergo less rigorous review by t he NRC; faiture to provide the infonnation will necessi t ate a detailed review or every question.)

Question Cognitive Level: 1 0 CFR Part 5 5 Content: Comments: Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 X 06/25/2009 Turkey Point ILC 25 NRC Examination Question 74 Unit 3 is operating at 100% power when the following alanns occur: A 9/2, PZR CONTROL HIILO PRESS B 6/3, POWER RANGE OVERPOWER ROD STOP B 6/4, POWER RANGE CHANNEL DEVIATION C 6/2 , SG B LEVEL DEVIA nON G 4/3, RCS METAL IMPACT G 5/2, AXIAL FLUX ADMIN LIMIT EXCEEDED What action should the crew take based on the above alanns? A Transfer 1 sl Stage Pressure Controller to operable channel B Place Pressurizer Pressure Controller in MANUAL C Place 3B FRV in MANUAL D Place rods in MANUAL Page 147 of 200

06/25/2009 Tu rk ey Point IL C 25 N R C Exa min a ti on Ques t io n 74 Unit 3 is operat in g at 1 00% power when th e following a l arms occu r: A 9/2 , PZR CONTROL H ULO PRESS 86/3, POWER RANGE OVERPOWER ROD STO P 86/4. POWER RANGE C H ANNEL DEVIATION C 6/2 , SG B LEVEL DEVIATION G 4/3 , RCS METAL IMP ACT G 5/2 , AX I AL FLUX ADMIN LIMI T EXCEEDED What act i on s h o ul d the c r ew take based o n th e above a l anns? A Transfer I S l Stage Pressure Controlle r to o p erab l e channel B Pl ace P re ssurize r Pressure Controlle r in MANUAL C Pl ace 38 FR V in MANUAL D Place rods in MANUAL Pa ge 1 47 o f 200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 74 KIA 02.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm

Reference:

3-0NOP-059.8

-all alarms would come in on N-44 failure. Question history: New Correct answer: D A Incorrect; failure not related to PT-446/447. Plausible; could diagnose rod insertion due to 446/447 failure. B Incorrect; Pressurizer control failure would not bring in other alarms. Plausible; could diagnose Pressurizer control failure. C Incorrect; not a FRV failure. Plausible; could diagnose FRV failure D Correct; all alarms would come in on N-44 failure. Cognitive level: 2 Need to analyze failure and determine what procedure to use. Page 1480[200

06/25/2009 Tu r key Point l LC 25 NRC Exam i nation Q u estion 74 KIA G2.4.45 Ab il ity to prioritize and interpret the significance of each annunc i a t or or a l arm

Reference:

3-0NO P-059.8 -all a l arms would come in on N-44 fai l u r e. Question h istory: New Co rr e ct a n s w e r: D A In correct; failure not r e l ated to PT-446/447. Pla u s i b l e; cou l d diagnose rod insertio n due 10 446/447 failure. B Incorrect; Pressurizer control failure wo u ld nol bring in other a i arnlS. Plausib l e; could diagnose Pressuri z er control fai l ure. C I ncorrect; not a FRV fai l u r e. Pla u sib l e; cou l d diagnose FRV fail u re o Correct; all alarms wou l d come i n on N-44 fai lur e. Cogniti v e level: 2 Need 10 anal y ze failure and detennine wha t procedure to use . Pa g e 14 80 1'200 Question #75 ES-401 Question 75 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Level Tier # Group # KJA# Importance Rating Proposed Question:

See attached Proposed Answer: B Explanation (Optional):

RO 3 G2.4.6 3-EOP-E-0 would isolate AFW to a faulted S/O off the FOP. Not isolated during perfonnance of the IOAs and the FOP is the first perfonned option listed. 6/25/2009 Form ES-401-5 SRO Technical Reference( s): .=..3-....::;E;:...:O;:...:P_--=E;....;-0"--=-04..:.;../..::..0=9/-=2=00.=..;9=--

___________

_ (Attach if not previously provided)

__________________

_ (including version/revision number) ___________________

_ Proposed references to be provided to applicants during examination:

Learning Objective:

6902348 Obi. 4 (As available)

Question Source: Bank# Modified Bank # ___ (Note changes or attach New Question History: Last NRC Exam parent) X (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the infofTTIation will necessitate a detailed review of every question.)

Question Cognitive Level: 10 CFR Part 55 Content: Comments:

Memory or Fundamental Knowledge Comprehension or Analysis 55.41 55.43 10 Oinna 2007 NRC examination question 99 X Que s ti on #75 ES-401 Question 75 Written Examination Question Worksheet Examination Outline Cross-

Reference:

Le vel Tier # Group # KIA # Imp ortance Rating Proposed Question: See attached Proposed A nswer: B E x planation (Optiona l): RO 3 G2.4.6 3-EOP-E-O wou ld isolate AFW t o a faulted S/G off th e FOP. Not i so l a t e d during performance of th e I OAs and the FOP is the first p erfonned option li s ted. 6n5 12 009 Form ES-401-5 SRO Te chnica l Reference (s): "'3-"'E"'O"P:..:-"'E"'

-0'-0"'4,,1"'09"'1"'2"'00"'9"-

___________

_ (A ttach if not previousl y p rov id ed) (including version/revision numbe-;r)------------------

Proposed r eferences to be provided to applicants during examination

Learning Objective: 6902348 Obi. 4 (As ava i labl e) Question Source: Bank# Modified Bank # New Question History: Last NRC E xa m __ ,,-(Note changes or atta c h parent) X (Op tional: Questions validated at the facility since 10/95 w ill generally undergo less rigorous review by the NRC; failure to prov i de the in f ormati on will necessi t ate 8 detai/ed rev ie w of ev e ry quest ion) Question Cognitive L evel: Memory or Fundamental Kn ow ledge X Comp rehensi on or Analysis 10 C FR Part 55 C o ntent: Comments: 55.41 55.43 10 Ginna 2007 N RC exa minati o n q u es ti o n 99 06/25/2009 Turkey Point ILC 25 NRC Examination Question 75

The Unit 4 reactor has tripped.

The 4A S I G is faulted. When should the BOP initially isolate AFW to the 4A S/G? A In 4-EOP-E-0, Reactor Trip or Safety Injection, during performance of the main body of the procedure. B In 4-EOP-E-0 , Reactor Trip or Safety Injection , when the Fold Out Page is directed.

C In 4-EOP-E-2, Faulted Steam Generator Isolation, during performance of the main body of the procedure. o In 4-EOP-E-2, Faulted Steam Generator Isolation , when the Fold Out Page is directed.

Page 149 o f 200

06/25/2009 Turke y Point IL C 25 NRC Exa minati on Que s tion 75

The U ni t 4 rea c tor h as tripped.

T h e 4A S/G i s faulted. When s h ou ld the BOP initi a lly i so late AFW t o th e 4A S/G? A In 4-E OP-E-O , Reactor T rip or Safety Inje ction, durin g p e rforman ce of th e main body o f the procedure. B In 4-EOP-E-D , Rea c tor Trip o r Safe t y in jec ti o n , whe n the Fold Out P age is dire c ted. C In 4-EOP-E-2 , Faulted Steam Ge n erator I so l ation , during perfonnance of the main body of the procedure. D In 4-EOP-E-2, Faulted S t ea m Genera t or I solatio n , w h e n the fold Out P age i s direc t ed. Pa ge 14 90[200 06/25/2009 Turkey Point ILC 25 NRC Examination Question 75 KIA G2.4.6 Knowledge of symptom based EOP mitigation strategies

Reference:

3-EOP-E-0 would isolate AFW to a faulted S/G offthe FOP. Not isolated during performance of the IOAs and the FOP is the first performed option listed. Question history: New Correct answer: B A Incorrect per above discussion. Plausible; would isolate feed to stop cooldown during performance of two-column part of procedure.

B Correct per above discussion.

C Incorrect per above discussion.

Plausible; would isolate feed to stop cooldown during performance of two-column part of procedure.

D Incorrect per above discussion.

Plausible; although E-2 doesn't have a FOP, someone without knowledge of the procedure format could assume it does since all of the other major EOPs do. Cognitive level: 1 Page 150 of 200

06/2512009 Turkey Point I LC 25 NRC Examination Question 75 KIA G2.4.6 Knowledge of symptom based EOr mitigation stra tegie s

Reference:

3-EOP-E-0 would isolate AFW to a faulted S/G offthe FOP. Not isolated during perfonnance ofl he IOAs and the FOP is the fi r s t perfonned opt i o n listed. Question hi story: New Correct answe r: B A I ncorrect per above discussion.

Plausible; would isolate feed to stop coo ld ow n during p erfonnancc of two-column part of procedure.

B Correc t per above discussion.

C In correct per above discussion. Pl a u s ible; would isolate feed to s t op coo l down during pcrfonnance of t wo-co lumn part of procedure.

o I ncorrect per above di scussion.

Pl a u s ibl e; although E-2 doesn't ha ve a FOP, so m eone without knowledge of th e procedure fonnat co uld assume it docs si n ce all of the ot h e r major EOPs do , Cognitive l evel: I Page 1 50 of200

@@ Line 2: / Line 2: @@
 | number = ML100670508
 | issue date = 12/11/2009
-| title = Turkey Point Initial Exam 2009-302 Draft RO Written Exam
+| title = Initial Exam 2009-302 Draft RO Written Exam
 | author name =
 | author affiliation = NRC/RGN-II

Person / Time
ML100670508
Site:	Turkey Point (DPR-031, DPR-041)
Issue date:	12/11/2009
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
50-250/09-302, 50-251/09-302 50-250/09-302, 50-251/09-302
Download: ML100670508 (262)
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ML100670508: Difference between revisions

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