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302 Initial Licensing Examination (RO & SRO)
	ML093010111
Person / Time
Site:	Turkey Point
Issue date:	10/28/2009
From:	; Florida Power & Light Co
To:	; NRC/RGN-II
References
	Download: ML093010111 (199)
	v • d • e

{{#Wiki_filter:ES-401 Name: Date: Site-Specific RO Written Examination Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Form ES-401-7 Facility/Unit: Turkey Point Units 3 & 4 Region: I D II X III D IV D Reactor Type: W X CE D BW D GE D Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours after the examination begins. Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent ES-401 Name: Date: Site-Specific RO Written Examination Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Form ES-401-7 Facility/Unit: Turkey Point Units 3 & 4 Region: I D II X III D IV D Reactor Type: W X CE D BW D GE D Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours after the examination begins. Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent

Turkey Point ILC 25 aJ{OKEY 1 C 57 B-2 D 58 C-3 D 59 C' 4 B 60 A 5 A 61 D 6 B 62 B 7 B 63 D 8 A 64 B 9 B 65 C 10 D 66 D 11 A 67 A 12 D 68 B 13 A 69 A 14 C 70 D 15 B 71 C 16 A n A 17 B 73 D 18 D 74 D 19 A 75 B 20 B 6 21 A 7 22 B 23 B 7 24 B 8 A 25 D 81 A 26 A 82 C, 27 D 83 D. 28 B 84 B 29 D 85 D 30 C 86 C 31 B 87 A 32 C 88 A 33 D 89 C 34 B 90 A 35 B 91 B 36 A 92 37 B 93 38 B 94 39 B 95 40 D 96 41 C

97.

42 B 9 43 A ito 44 C 45 C 46 C 47 C 48 C 49 D 50 C 51 C 52 D 53 A 54 D' 55 C 56 B' Turkey Point ILC 25 aROKEY c 57 B 2 D 58 C 3 D 59 C 4 B 60 A 5 A 61 D 6 B 62 B 7 B 63 D 8 A 64 B 9 B 65 C 10 D 66 D 11 A 67 A 12 D 68 B 13 A 69 A 14 C 70 D 15 B 71 C 16 A A 17 B D 18 D D 19 A B 20 B 21 A 22 B 23 B A 24 B 25 D 26 A 82 27 D 83 28 B 84 29 D 85 30 C 86 31 B 87 32 C 88 33 D 89 34 B 90 35 B 91 36 A 92 37 B 93 38 B 94 39 B 95 40 D 96 41 C 97 42 B 9 43 A ~to 44 c 45 C 46 C 47 C 48 C 49 D 50 C 51 C 52 D 53 A 54 D 55 C 56 B'

Turkey Point ILC 25 Question 1 Unit 3 is at 100% power. Pressurizer pressure is decreasing. The bottom two rows of LEDs on the acoustic monitor are lit. The PORV tailpipe temperature is 220oP. The safety valve tailpipe temperatures are 130op. What can be determined by these indications? A The specific PORV that is leaking B The specific safety valve that is leaking C A PORV is leaking, but cannot determine which one D A safety valve is leaking, but cannot determine which one Turkey Point ILC 25 Question 1 Unit 3 is at 100% power. Pressurizer pressure is decreasing. The bottom two rows of LEDs on the acoustic monitor are lit. The PORV tailpipe temperature is 220°F. The safety valve tailpipe temperatures are 130°F. What can be determined by these indications? A The specific PORV that is leaking B The specific safety valve that is leaking C A PORV is leaking, but cannot determine which one D A safety valve is leaking, but cannot determine which one

Turkey Point ILC 25 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. MOV-4-843 A & B, HHSI to Cold Leg MOV, are both closed. RCS Subcooling is 40°F. For the given plant conditions, which one of the following describes RCP operation in accordance with 4-EOP-E-l, and the basis for this action? 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. Turkey Point ILC 25 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. MOV-4-843 A & B, HHSI to Cold Leg MOV, are both closed. ReS Subcooling is 40°F. For the given plant conditions, which one of the following describes RCP operation in accordance with 4-EOP-E-l, and the basis for this action? 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.

Turkey Point ILC 25 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 with a negative 0.1 dpm SUR. 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. In accordance with 3-EOP-F-0, Critical Safety Function Status Trees, what is the color of the critical safety function the unit is in and what procedure will the crew implement first? The plant meets the conditions for alan __ (>...=1:...<.) __ path. The crew will implement (2) first. (1) A Orange B Red C Orange D Red (2) 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-S.1, Response to Nuclear Power GenerationlATWS 3-EOP-FR-S.1, Response to Nuclear Power GenerationlATWS Turkey Point ILC 25 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 with a negative 0.1 dpm SUR. 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. In accordance with 3-EOP-F-0, Critical Safety Function Status Trees, what is the color of the critical safety function the unit is in and what procedure will the crew implement first? The plant meets the conditions for alan __ C>...:I,-"-) __ path. The crew will implement (2) first. (1) A Orange B Red C Orange D Red (2) 3-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-S.1, Response to Nuclear Power GenerationJATWS 3-EOP-FR-S.1, Response to Nuclear Power GenerationJATWS

Turkey Point ILC 25 Question 4 Unit 3 is at 35% power. The 3A RCP breaker has just tripped. Which one of the following statements correctly describes how the plant will respond and the reason a reactor trip is necessary? A The reactor will automatically trip to maintain DNBR within acceptable limits. B The reactor will NOT automatically trip. It must be manually tripped to maintain DNBR within acceptable limits C The reactor will automatically trip to maintain power density (kw/ft) within acceptable limits. D The reactor will NOT automatically trip. It must be manually tripped to maintain power density (kw/ft) within acceptable limits. Turkey Point ILC 25 Question 4 Unit 3 is at 35% power. The 3A RCP breaker has just tripped. Which one of the following statements correctly describes how the plant will respond and the reason a reactor trip is necessary? A The reactor will automatically trip to maintain DNBR within acceptable limits. B The reactor will NOT automatically trip. It must be manually tripped to maintain DNBR within acceptable limits C The reactor will automatically trip to maintain power density (kw/ft) within acceptable limits. D The reactor will NOT automatically trip. It must be manually tripped to maintain power density (kw/ft) within acceptable limits.

Turkey Point ILC 25 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: ~ FI-3-122, Charging Line Flow Indicator, indicates 10 gpm and decreasing ~ G 112, CHARGING PUMPS HI SPEED, is in alarm ~ A 9/3, PZR CONTROL HIILO LEVEL, is in alarm ~ VCT level is 25% and increasing ~ The SNPO reports abnormal noise coming from the 3A Charging Pump and it is vibrating. In accordance with 3-0NOP-047.1, Loss of Charging Flow in Modes 1 Through 4, which one of the following is the cause of the above event? The 3A Charging Pump... A is becoming gas bound. B controller has lost Instrument Air. C suction piping is leaking. D discharge piping is leaking. Turkey Point ILC 25 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: FI 122, Charging Line Flow Indicator, indicates 10 gpm and decreasing G 112, CHARGING PUMPS HI SPEED, is in alarm A 913, PZR CONTROL HIILO LEVEL, is in alarm VCT level is 25% and increasing The SNPO reports abnormal noise coming from the 3A Charging Pump and it is vibrating. In accordance with 3-0NOP-047.1, Loss of Charging Flow in Modes 1 Through 4, which one of the following is the cause of the above event? The 3A Charging Pump... A is becoming gas bound. B controller has lost Instrument Air. C suction piping is leaking. D discharge piping is leaking.

Turkey Point ILC 25 Question 6 Initial conditions: Unit 4 operated for 2 effective full power 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 Note: 1.3483 (MWDIMTU)/EFPH A 40 to 45 minutes B 55 to 60 minutes C 85 to 90 minutes D 185 to 190 minutes Turkey Point ILC 25 Question 6 Initial conditions: Unit 4 operated for 2 effective full power 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 Note: 1.3483 (MWD/MTU)/EFPH A 40 to 45 minutes B 55 to 60 minutes C 85 to 90 minutes D 185 to 190 minutes

Turkey Point ILC 25 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)

0)

(2) A run at max speed all Charging Pumps B run at max speed one Charging Pump C run at min speed all Charging Pumps D run at min speed one Charging Pump Turkey Point ILC 25 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 _-,(~1c..L) __ 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 run at min speed all Charging Pumps D run at min speed one Charging Pump

Turkey Point ILC 25 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 respond within the first minute? Liquid space Vapor space A Increase Increase B Increase Decrease C Decrease Decrease D Decrease Increase Turkey Point ILC 25 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 respond within the first minute? Liquid space Vapor space A Increase Increase B Increase Decrease C Decrease Decrease D Decrease Increase

Turkey Point ILC 25 Question 9 Unit 4 has experienced a Steam Generator tube rupture. Off-site power has been lost and will not be restored for 24 hours. In accordance with 4-EOP-E-3, Steam Generator Tube Rupture, how will the RCS cooldown and depressurization to terminate safety injection be conducted? The crew will dump steam to (1) and depressurize the RCS using (2) (1) (2) A atmosphere auxiliary spray B atmosphere aPORV C the condenser auxiliary spray D the condenser aPORV Turkey Point ILC 25 Question 9 Unit 4 has experienced a Steam Generator tube rupture. Off-site power has been lost and will not be restored for 24 hours. In accordance with 4-EOP-E-3, Steam Generator Tube Rupture, how will the RCS cooldown and depressurization to terminate safety injection be conducted? The crew will dump steam to (1) and depressurize the RCS using (2) (1) (2) A atmosphere auxiliary spray B atmosphere aPORV C the condenser auxiliary spray D the condenser aPORV

Turkey Point ILC 25 Question 10 Unit 4 was initially at 100% power. A Feedline break developed to the 4A S/G inside Containment at the Containment penetration. 4A S/G pressure is 400 psig at the moment of S/G isolation. Which one of the following describes the effect of this event? A RCS temperatures lower prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. B RCS temperatures lower prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation. C RCS temperatures rise prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. D RCS temperatures rise prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation. Turkey Point ILC 25 Question 10 Unit 4 was initially at 100% power. A Feedline break developed to the 4A S/G inside Containment at the Containment penetration. 4A S/G pressure is 400 psig at the moment of S/G isolation. Which one of the following describes the effect of this event? A RCS temperatures lower prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. B RCS temperatures lower prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation. C RCS temperatures rise prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. D RCS temperatures rise prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation.

Turkey Point ILC 25 Question 11 Unit 3 has experienced a loss of all AC power. The crew has determined that a source of power is not available. In accordance with 3-EOP-ECA-O.O, Loss of All AC Power, why are RCP Seal Manual Isolation Valves (3-297 AlBIC) and the RCP Seal Cooling Water Outlet Valve (MOV 626) closed? 3-297 AlBIC are closed to prevent (1) (2) A (1) thermal 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) thermal shocking the RCPs D (1) thermal shocking the RCPs (2) thermal shocking the RCPs Turkey Point ILC 25 Question 11 Unit 3 has experienced a loss of all AC power. The crew has determined that a source of power is not available. In accordance with 3-EOP-ECA-O.O, Loss of All AC Power, why are RCP Seal Manual Isolation Valves (3-297 AlBIC) and the RCP Seal Cooling Water Outlet Valve (MOV 626) closed? 3-297 AlBIC are closed to prevent (1) (2) A (1) thermal 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) thermal shocking the RCPs D (1) thermal shocking the RCPs (2) thermal shocking the RCPs

Turkey Point ILC 25 Question 12 Unit 3 experienced a loss of offsite power. The 3A and 3B 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. B involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. C involve an actual or potential substantial degradation ofthe level of safety of the plant. D indicate a potential degradation of the level of safety of the plant. Turkey Point ILC 25 Question 12 Unit 3 experienced a loss of offsite power. The 3A and 3B 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. B 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.

Turkey Point ILC 25 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 Panel3P07. VCT level indicator LI-3-112 indicates 25%. VCT level indicator LI-3-115 indicates zero level. Annunciator A 4/6, VCT HIILO 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. Turkey Point ILC 25 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 Pane13P07. VCT level indicator LI-3-112 indicates 25%. V CT level indicator LI 115 indicates zero level. Annunciator A 4/6, VCT HIILO 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.

Turkey Point ILC 25 Question 14 Turkey Point has experienced a long-term total loss of Instrument Air. In accordance with O-ONOP-013, Loss ofInstrument Air, 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. Turkey Point ILC 25 Question 14 Turkey Point has experienced a long-term total loss of Instrument Air. In accordance with O-ONOP-013, Loss ofInstrument Air, how is CV-3-2046A, 3A EDG Level Control Valve, opened to fill the 3A EDG day tank? CV-3-2046A 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.

Turkey Point ILC 25 Question 15 The crew is performing 3-EOP-ECA-1.2, LOCA outside Containment. In accordance with 3-EOP-ECA-1.2 which one of the following leak paths outside Containment will be isolated first? A SI Hot Leg Injection Valves B RHR Suction Valves C RHR Discharge to Cold Legs D SI to Cold Leg Isolation Valves Turkey Point ILC 25 Question 15 The crew is performing 3-EOP-ECA-l.2, LOCA outside Containment. In accordance with 3-EOP-ECA-I.2 which one of the following leak paths outside Containment will be isolated first? A SI Hot Leg Injection Valves B RHR Suction Valves C RHR Discharge to Cold Legs D SI to Cold Leg Isolation Valves

Turkey Point ILC 25 Question 16 Initial conditions: Unit 3 is in Mode 3. The 3B Steam Generator Feedpump not available. Subsequently: The Unit 3 Startup Transformer locks out. The Auxiliary Feedwater Pumps are not available. The Main Feedwater Pumps are 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 D A SSGFP NOT available B SSGFP NOT available Turkey Point ILC 25 Question 16 Initial conditions: Unit 3 is in Mode 3. The 3B Steam Generator Feedpump not available. Subsequently: The Unit 3 Startup Transformer locks out. The Auxiliary Feedwater Pumps are not available. The Main Feedwater Pumps are 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 D A SSGFP NOT available B SSGFP NOT available

Turkey Point ILC 25 Question 17 Unit 3 has experienced a loss of emergency coolant recirculation. RWST level is 59,000 gallons. In accordance with 3-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation, what action will the crew take and why? 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 RWST. D only the Charging Pumps and Containment Spray Pumps. This will extend the availability of the RWST. Turkey Point ILC 25 Question 17 Unit 3 has experienced a loss of emergency coolant recirculation. RWST level is 59,000 gallons. In accordance with 3-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation, what action will the crew take and why? 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 RWST. D only the Charging Pumps and Containment Spray Pumps. This will extend the availability of the RWST.

Turkey Point ILC 25 Question 18 Unit 3 has experienced a reactor trip and safety injection. The crew has entered 3-EOP-E-2, Faulted Steam Generator Isolation. The 3A S/G is faulted and its wide range level is 8% and lowering. Which one of the following is correct? In accordance with E-2, the crew will stabilize __ (",-,,1,-,-) __ temperatures using steam dumps. This is to minimize RCS (2) -ill_ (2) A cold leg cooldown B cold leg pressure mcrease C hot leg cooldown D hot leg pressure mcrease Turkey Point ILC 25 Question 18 Unit 3 has experienced a reactor trip and safety injection. The crew has entered 3-EOP-E-2, Faulted Steam Generator Isolation. The 3A S/G is faulted and its wide range level is 8% and lowering. Which one of the following is correct? In accordance with E-2, the crew will stabilize __ (""ICJ.) __ temperatures using steam dumps. This is to minimize RCS (2) -ID_ (2) A cold leg cooldown B cold leg pressure mcrease C hot leg cooldown D hot leg pressure mcrease

Turkey Point ILC 25 Question 19 Rod M-8 in Bank D Group 1 dropped into the core earlier. The crew is recovering rod M-8. Which lift coil disconnect switches will the crew place to disconnect in order to retrieve M-8 and why will the RO record the Bank D Group 1 step counter position? The crew will place the lift coil disconnect switches for (1) to the disconnect position (toggle switch down). The RO will record Bank D Group 1 step counter position as a reference point to (2)

0)

(2) A all rods in Bank D except M-8 withdraw M-8 B all rods in Bank D except M-8 reset the pulse analog converter C only M-8 withdraw M-8 D only M-8 reset the pulse analog converter Turkey Point ILC 25 Question 19 Rod M-8 in Bank D Group 1 dropped into the core earlier. The crew is recovering rod M-8. Which lift coil disconnect switches will the crew place to disconnect in order to retrieve M-8 and why will the RO record the Bank D Group 1 step counter position? The crew will place the lift coil disconnect switches for (1) to the disconnect position (toggle switch down). The RO will record Bank D Group 1 step counter position as a reference point to (2) (1) (2) A all rods in Bank D except M-8 withdraw M-8 B all rods in Bank D except M-8 reset the pulse analog converter C only M-8 withdraw M-8 D only M-8 reset the pulse ana10 g converter

Turkey Point ILC 25 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 without SI occurred 15 minutes ago and Tcolds have decreased to 530°F. Shutdown margin is not assured. B A reactor trip without SI 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 tlH could exceed design limits. Turkey Point ILC 25 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 without SI occurred 15 minutes ago and Tcolds have decreased to 530°F. Shutdown margin is not assured. B A reactor trip without SI 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 t1H could exceed design limits.

Turkey Point ILC 25 Question 21 Initial conditions: Unit 4 is at 3% power. All Pressurizer controls are in automatic. Subsequently I&C is performing 4-SMI-041.11, Pressurizer Level Protection Loops Quarterly Test. Pressurizer level control switch is in position 3. I&C placed Loop L-459 for LT-4-459 in the tripped condition. Concurrently, LT 461 fails high. How will the unit initially respond to the event? A Backup heaters will energize B The unit will trip C No immediate effect because LT-4-461 is selected for backup D No immediate effect because L T 459 is bypassed for testing Turkey Point ILC 25 Question 21 Initial conditions: Unit 4 is at 3% power. All Pressurizer controls are in automatic. Subsequently I&C is performing 4-SMI -041.11, Pressurizer Level Protection Loops Quarterly Test. Pressurizer level control switch is in position 3. I&C placed Loop L-459 for LT-4-459 in the tripped condition. Concurrently, L T 461 fails high. How will the unit initially respond to the event? A Backup heaters will energize B The unit will trip C No immediate effect because L T 461 is selected for backup D No immediate effect because L T 459 is bypassed for testing

Turkey Point ILC 25 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 high flux at shutdown 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 D 50 cps will automatically actuate Turkey Point ILC 25 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

0). If the high flux at shutdown alarm actuates, the Containment evacuation alarm (2).

0)

(2) A 32 cps must be manually actuated B 32 cps will automatically actuate C 50 cps must be manually actuated D 50 cps will automatically actuate

Turkey Point ILC 25 Question 23 The A Monitor Tank (MT) is being released when the following occurred:

Annunciator H 1/4 PRMS HI RADIA nON is received in the Control Room.
PRMS-R-18, Waste Disposal Liquid Effluent Monitor, high alarm is validated.
MT A level is 75% and slowly lowering.
RCV-018, Liquid Waste Discharge Valve, indicates as follows:

~ Red light - on ~ Green light - on In accordance with 3-0NOP-067, Radioactive Effluent Release, which of the following is correct? A RCV -018 is open. Close RCV -018 from VPB with keyswitch. B RCV -018 is open. Close RCV -018 from the waste boron panel. C RCV-018 is closed. Flush R-18 and re-initiate the release. D RCV-018 is closed. IfR-18 alarm clears, re-initiate the release. Turkey Point ILC 25 Question 23 The A Monitor Tank (MT) is being released when the following occurred:

Annunciator H 114 PRMS HI RADIATION is received in the Control Room.
PRMS-R-18, Waste Disposal Liquid Effluent Monitor, high alarm is validated.
MT A level is 75% and slowly lowering.
RCV-OI8, Liquid Waste Discharge Valve, indicates as follows:

~ Red light - on ~ Green light - on In accordance with 3-0NOP-067, Radioactive Effluent Release, which of the following is correct? A RCV-OI8 is open. Close RCV-OI8 from VPB with keyswitch. B RCV-OI8 is open. Close RCV-OI8 from the waste boron panel. C RCV-OI8 is closed. Flush R-18 and re-initiate the release. D RCV-OI8 is closed. IfR-18 alarm clears, re-initiate the release.

Turkey Point ILC 25 Question 24 In accordance with O-ONOP-I05, Control Room Evacuation, which of these actions is the Unit 3 RO expected to perform before leaving the Control Room? A Trip the reactor Close the MSIV s Verify RCPs running B Trip the reactor Trip the RCPs Close PORV block valves C Trip the Steam Generator Feedwater Pumps Close MSR Steam Stops Close PORV block valves D Trip the main turbine Close the MSIVs Start 3B Charging Pump Turkey Point ILC 25 Question 24 In accordance with O-ONOP-I05, Control Room Evacuation, which of these actions is the Unit 3 RO expected to perform before leaving the Control Room? A Trip the reactor Close the MSIV s Verify RCPs running B Trip the reactor Trip the RCPs Close PORV block valves C Trip the Steam Generator Feedwater Pumps Close MSR Steam Stops Close PORV block valves D Trip the main turbine Close the MSIV s Start 3B Charging Pump

Turkey Point ILC 25 Question 25 Initial Conditions: Unit 4 was at 100% power. 4A QSPDS has been declared inoperable because of aPT 404 failure. Subsequently: Unit 4 experienced a LOCA with Safety Injection. 50 gpm is indicated on FI-4-943, Safety Injection Flow. RWST level is also decreasing at 50 gpm. The crew entered 4-EOP-FR-C.2, Degraded Core Cooling. QSPDS Train B now indicates the following: Thots are all approximately 525°F. RCS subcooling is 126°F. Which of the following correctly describes QSPDS Train B indication and required action(s)? LJ PT-'-/-¥ci./!PT-i/-£/d? 2G5 11-01 /..V) I'-,./?$$t-V'~ '~r1S/r7/#~-<:: 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 approximately 2210 psig. Manually calculate subcooling. Turkey Point ILC 25 Question 25 Initial Conditions: Unit 4 was at 100% power. 4A QSPDS has been declared inoperable because of a PT-4-404 failure. Subsequently: Unit 4 experienced a LOCA with Safety Injection. 50 gpm is indicated on FI-4-943, Safety Injection Flow. RWST level is also decreasing at 50 gpm. The crew entered 4-EOP-FR-C.2, Degraded Core Cooling. QSPDS Train B now indicates the following: Thots are all approximately 525°F. RCS subcooling is 126°F. Which of the following correctly describes QSPDS Train B indication and required action(s)? PT-Lf-*li/ljJT-t/-i~ Pc.:s Jto-f /..Ptj f?-,.L?$:>t-V'~ '~rJ5/n///~-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 approximately 2210 psig. Manually calculate subcooling.

Turkey Point ILC 25 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-l.l, SI Termination. All SI actuation 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 running. They auto started when Pressurizer pressure dropped below 1835 psig. 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. Turkey Point ILC 25 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 actuation 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 when Pressurizer pressure dropped below 1835 psig. 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.

Turkey Point ILC 25 Question 27 A Containment purge was in progress on Unit 3. A LOCA occurred. The crew is responding to high containment radiation level. POV-3-2603, 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 2603 closed by pulling its fuse behind VP A. D Fail POV-3-2603 closed by pulling its fuse behind VPB. Turkey Point ILC 25 Question 27 A Containment purge was in progress on Unit 3. A LOCA occurred. The crew is responding to high containment radiation level. POV-3-2603, 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 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 VPA. D Fail POV-3-2603 closed by pulling its fuse behind VPB.

Turkey Point ILC 25 Question 28 Safety Injection and Phase A have occurred on Unit 3. The Phase A signal has NOT been reset. Which one of the following states what effect this will have on RCP Number 1 seal leak off flow and why? Number 1 seal leak off flow will... A decrease because VCT pressure has increased. B decrease because the backpressure has increased. C go to and remain at zero because the RCP Seal Return to VCT is closed. D go to and remain at zero because #1 Seal LeakoffIsolation Valves are closed. Turkey Point ILC 25 Question 28 Safety Injection and Phase A have occurred on Unit 3. The Phase A signal has NOT been reset. Which one of the following states what effect this will have on RCP Number 1 seal leak off flow and why? Number 1 seal leak off flow will... A decrease because VCT pressure has increased. B decrease because the backpressure has increased. C go to and remain at zero because the RCP Seal Return to VCT is closed. D go to and remain at zero because # 1 Seal Leakoff Isolation Valves are closed.

Turkey Point ILC 25 Question 29 Annunciator G 211, RCP A STANDPIPE HI LEVEL, has alarmed. 3A RCP #1 sealleakoffflow has decreased from 2 gpm to 1 gpm. In accordance with 3-0NOP-041.1, Reactor Coolant Pump Off-Normal, which of the following is the cause of the above conditions? A RV-3-382, Seal Return Relief Valve, leaking by B CV-3-303A, 3A RCP Seal LeakoffIsolation Valve failed closed C 3A RCP number 1 seal failure D 3A RCP number 2 seal failure Turkey Point ILC 25 Question 29 Annunciator G 211, RCP A STANDPIPE HI LEVEL, has alarmed. 3A RCP #1 sealleakoffflow has decreased from 2 gpm to 1 gpm. In accordance with 3-0NOP-041.1, Reactor Coolant Pump Off-Normal, which of the following is the cause of the above conditions? A RV-3-382, Seal Return Relief Valve, leaking by B CV-3-303A, 3A RCP Seal LeakoffIsolation Valve failed closed C 3A RCP number 1 seal failure D 3A RCP number 2 seal failure

Turkey Point ILC 25 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 Immediately 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 48 hours Turkey Point ILC 25 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 Immediately 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 48 hours

Turkey Point ILC 25 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----'-'(l"-,t.) __. Flow to the core will (2) (1) (2) A decrease remain the same B decrease decrease C Increase remain the same D Increase decrease Turkey Point ILC 25 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 0) . Flow to the core will (2) (1) (2) A decrease remain the same B decrease decrease C mcrease remain the same D mcrease decrease

Turkey Point ILC 25 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 Turkey Point ILC 25 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

Turkey Point ILC 25 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 of the following identifies the operability of the 3A SI Accumulator and why? The 3A SI accumulator is... A OPERABLE. All Tech Spec limits are met. B INOPERABLE. The water level is out of specification. C INOPERABLE. The cover gas pressure is out of specification. D INOPERABLE. The boron concentration is out of specification. Turkey Point ILC 25 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 of the following identifies the operability of the 3A SI Accumulator and why? The 3A SI accumulator is... A OPERABLE. All Tech Spec limits are met. B INOPERABLE. The water level is out of specification. C INOPERABLE. The cover gas pressure is out of specification. D INOPERABLE. The boron concentration is out of specification.

Turkey Point ILC 25 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 and is INOPERABLE. Based on the above conditions what is/are the MINIMUM action(s) required to be taken in accordance with Technical Specifications? A Restore PORV to OPERABLE status AND close the associated block valve with power maintained to the block valve. B Restore PORV to OPERABLE status OR close the associated block valve with power maintained to the block valve. C Restore PORV to OPERABLE status AND close the associated block valve with power removed to the block valve. D Restore PORV to OPERABLE status OR close the associated block valve with power removed to the block valve. Turkey Point ILC 25 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 and is INOPERABLE. Based on the above conditions what is/are the MINIMUM action(s) required to be taken in accordance with Technical Specifications? A Restore PORV to OPERABLE status AND close the associated block valve with power maintained to the block valve. B Restore PORV to OPERABLE status OR close the associated block valve with power maintained to the block valve. C Restore PORV to OPERABLE status AND close the associated block valve with power removed to the block valve. D Restore PORV to OPERABLE status OR close the associated block valve with power removed to the block valve.

Turkey Point ILC 25 Question 35 Which one of the following describes the operation of 3D 4kV bus feeder breakers 3AB19 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 if3AB19 is opened. B 3AD06 must be closed first. 3AB19 will trip if3AD06 is opened. C 3AB19 must be closed first. 3AD06 will remain closed if3AB19 is opened. D 3AD06 must be closed first. 3AB 19 will remain closed if 3AD06 is opened. Turkey Point ILC 25 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. 3AB 19 will remain closed if 3AD06 is opened.

Turkey Point ILC 25 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 Turkey Point ILC 25 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

Turkey Point ILC 25 Question 37 What are the setpoints for the Pressurizer Backup Heaters energization (1) and Letdown isolation (2)7 (1) PZR press of: (2)PZR level of: A 2210 psig 12% B 2210 psig 14% C 2220 psig 12% D 2220 psig 14% Turkey Point ILC 25 Question 37 What are the setpoints for the Pressurizer Backup Heaters energization (1) and Letdown isolation (2)7 (1) PZR press of: (2)PZR level of: A 2210 psig 12% B 2210 psig 14% C 2220 psig 12% D 2220 psig 14%

Turkey Point ILC 25 Question 38 Initial conditions: Unit is at 2% power. j Train 4B RPS testing is in progress. /N/!,.; US! biRo/? n The 4B Reactor Trip Bypass Breake1)BJacked in and closed. '.1 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 4DOI 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. Turkey Point ILC 25 Question 38 Initial conditions:

Unit is at 2% power.

) Train 4B RPS testing is in progress. Wi!,.; ?tSf boP.&' n The 4B Reactor Trip Bypass Breake1)BJ'acked in and closed. < -1 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 4DOI 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.

Turkey Point ILC 25 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 will the crew implement? A 3-0NOP-003.6, Loss of 120V Vital Instrument Panel 3P06 B 3-0NOP-003.7, Loss of 120V Vital Instrument Panel 3P07 C 3-0NOP-003.S, Loss of 120V Vital Instrument Panel3POS D 3-0NOP-003.9, Loss of 120V Vital Instrument Panel 3P09 Turkey Point ILC 25 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 will the crew implement? A 3-0NOP-003.6, Loss of 120V Vital Instrument Panel 3P06 B 3-0NOP-003.7, Loss of 120V Vital Instrument Panel 3P07 C 3-0NOP-003.8, Loss of 120V Vital Instrument Panel3P08 D 3-0NOP-003.9, Loss of 120V Vital Instrument Panel 3P09

Turkey Point ILC 25 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

0)

. The Unit 3 HHSI Pumps' suction will be aligned 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 Turkey Point ILC 25 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

0)

. The Unit 3 HHSI Pumps' suction will be aligned 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

Turkey Point ILC 25 Question 41 Unit 3 has experienced a spurious safety injection. The RO has just commenced performance of 3-EOP-E-O, 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 D Three Four Turkey Point ILC 25 Question 41 Unit 3 has experienced a spurious safety injection. The RO has just commenced performance of 3-EOP-E-O, 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 D Three Four

Turkey Point ILC 25 Question 42 Initial conditions Unit 4 Containment temperature at 1100P All Steam Generator narrow range levels on program at 60% Subsequently: CCW flow to the NCCs is lost Containment temperature has increased to 125°P All Steam Generator narrow range levels on program at 60% Steam Generator secondary system mass with the Containment at 125°P is (1) than at 11 oop. This is because the (2) leg density has decreased. (1) (2) A less variable B less reference C greater variable D greater reference Turkey Point ILC 25 Question 42 Initial conditions Unit 4 Containment temperature at 110°F All Steam Generator narrow range levels on program at 60% Subsequently: CCW flow to the NCCs is lost Containment temperature has increased to 125°F All Steam Generator narrow range 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 D greater reference

Turkey Point ILC 25 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 880 A & B will open. B The CSPs will start. MOV 880 A & B will NOT open. C The CSPs will NOT start. MOV 880 A & B will open. D The CSPs will NOT start. MOV 880 A & B will NOT open. Turkey Point ILC 25 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 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 880 A & B will open. D The CSPs will NOT start. MOV 880 A & B will NOT open.

Turkey Point ILC 25 Question 44 Initial conditions: Unit 3 is at 100% power. The RO has recently performed a dilution to compensate for fuel bumup. Subsequently, the following indications are noted in Control Room: Power Range NIs 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 by inserting control rods. Turkey Point ILC 25 Question 44 Initial conditions: Unit 3 is at 100% power. The RO has recently performed a dilution to compensate for fuel bumup. Subsequently, the following indications are noted in Control Room: Power Range NIs 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 by inserting control rods.

Turkey Point ILC 25 Question 45 Unit 3 was at 100% when 3P06 was lost. 3A S/G level is increasing slowly. The BOP is reducing feed to the 3A S/G when the following actuate: ~ Annunciator C 2/1, SG A NARROW RANGE HI LEVEL ~ Annunciator C 5/1, SG A STEAM> FEED ~ Bistable status light STM-FW FLOW DEV FC 478 Bl 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 A reactor trip is NOT required. The BOP should continue reducing feed flow. B A reactor trip is NOT required. The BOP should stop reducing feed flow. C The RO should trip the reactor. SI is NOT required. D The RO should trip the reactor. SI is required. Turkey Point ILC 25 Question 45 Unit 3 was at 100% when 3P06 was lost. 3A S/G level is increasing slowly. The BOP is reducing feed to the 3A S/G when the following actuate: Annunciator C 211, SG A NARROW RANGE HI LEVEL Annunciator C 511, SG A STEAM> FEED Bistable status light STM-FW FLOW DEV FC 478 Bl 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 A reactor trip is NOT required. The BOP should continue reducing feed flow. B A reactor trip is NOT required. The BOP should stop reducing feed flow. C The RO should trip the reactor. SI is NOT required. D The RO should trip the reactor. SI is required.

Turkey Point ILC 25 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. Turkey Point ILC 25 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.

Turkey Point ILC 25 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. Turkey Point ILC 25 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.

Turkey Point ILC 25 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? 3A4kVBus 3B 4kVBus A Deenergized Deenergized B Deenergized Energized C Energized Deenergized D Energized Energized Turkey Point ILC 25 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 4kV Bus 3B 4kV Bus A Deenergized Deenergized B Deenergized Energized C Energized Deenergized D Energized Energized

Turkey Point ILC 25 Question 49 The PTN switchyard deenergized. Only the 3B EDG started. The Unit 4 crew is performing 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 DeS? 4D01 4D23 A 2 hours 2 hours B 2 hours greater than 24 hours e greater than 24 hours 2 hours D greater than 24 hours greater than 24 hours Turkey Point ILC 25 Question 49 The PTN switchyard de energized. Only the 3B EDG started. The Unit 4 crew is performing 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? 4D01 4D23 A 2 hours 2 hours B 2 hours greater than 24 hours C greater than 24 hours 2 hours D greater than 24 hours greater than 24 hours

Turkey Point ILC 25 Question 50 Both units are at 100% power. The ANPO reports the following EDG lube oil temperatures: y 4A EDG 160°F Y 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 Turkey Point ILC 25 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

Turkey Point ILC 25 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. Turkey Point ILC 25 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.

Turkey Point ILC 25 Question 52 Chemistry reports an increase in gross equivalent iodine and 100lEbar activity. Based on the above report, complete the following. Process 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 mRfhr Crud D mRfhr Fission products Turkey Point ILC 25 Question 52 Chemistry reports an increase in gross equivalent iodine and IOO/Ebar activity. Based on the above report, complete the following. Process 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 mR/hr Crud D mR/hr Fission products

Turkey Point ILC 25 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: y CCW Heat Exchanger outlet temperature is currently 118°F and stable. y Annunciator E 2/2, TURB BEARING HI TEMP, is in alarm. y Turbine bearing temperatures are 181°F and slowly increasing. y 3A and 3B TPCW Heat Exchangers are at 4200 gpm ICW flow. y 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-011, Screen Wash System/Intake Malfunction. C Increase cooling water flow to the turbine oil cooler and implement 3-0NOP-011, Screen Wash System/Intake Malfunction. D Enter into Technical Specifications 3.0.3 and commence a reactor shutdown per 3-0NOP-100, Fast Load Reduction. Turkey Point ILC 25 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 alarm. ~ 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-011, Screen Wash System/Intake Malfunction. C Increase cooling water flow to the turbine oil cooler and implement 3-0NOP-011, Screen Wash System/Intake Malfunction. D Enter into Technical Specifications 3.0.3 and commence a reactor shutdown per 3-0NOP-100, Fast Load Reduction.

Turkey Point ILC 25 Question 54

PTN has exper~enced a dual-unit loss of off-site power. -.;t ~

~'f/ J 1-.::.1 rev t:f 1<" The 3B EDG dId not start. ~/..p-.(?n.P.-"'C;;'2 ~( What is the availability of the following air compressors? A 3CM, Unit 3 Instrument Air Motor Compressor, is available OCM!, Service Air Compressor, is available B 3CM, Unit 3 Instrument Air Motor Compressor, is available OCM!, Service Air Compressor, is NOT available C 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCM!, Service Air Compressor, is available D 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCM!, Service Air Compressor, is NOT available Turkey Point ILC 25 Question 54 PTN has exper~enced a dual-unit loss of off-site power. -.-tt ('~'f/j 1-.:::-1 '1Cvt-;( I" The 3B EDG dId not start. /I~- ~n<.t?-""1;' 2-..n(. What is the availability of the following air compressors? A 3CM, Unit 3 Instrument Air Motor Compressor, is available OCMl, Service Air Compressor, is available B 3CM, Unit 3 Instrument Air Motor Compressor, is available OCMl, Service Air Compressor, is NOT available C 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCMl, Service Air Compressor, is available D 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCMl, Service Air Compressor, is NOT available

Turkey Point ILC 25 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. Turkey Point ILC 25 Question 55 Unit 3 is in Mode 1. Containment temperature is II8°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.

Turkey Point ILC 25 Question 56 HCV 121, Charging Flow to Regen Heat Exchanger Control Valve, is full open. How is the controller for HCV 121 adjusted to decrease charging line flow under normal conditions and how does HCV 121 fail on loss of Instrument Air? The demand on the controller for HCV 121 is (1) to decrease charging line flow. HCV 121 fails (2) on loss ofInstrument Air. (1) (2) A decreased from 100% Open B increased from 0% Open C decreased from 100% Closed D increased from 0% Closed Turkey Point ILC 25 Question 56 HCV 121, Charging Flow to Regen Heat Exchanger Control Valve, is full open. How is the controller for HCV 121 adjusted to decrease charging line flow under normal conditions and how does HCV 121 fail on loss of Instrument Air? The demand on the controller for HCV 121 is (1) to decrease charging line flow. HCV 121 fails (2) on loss of Instrument Air. (1) (2) A decreased from 100% Open B increased from 0% Open C decreased from 1 00% Closed D increased from 0% Closed

Turkey Point ILC 25 Question 57 In accordance with O-ADM-209, Equipment Tagging and Labeling, how can post-accident instrumentation be identified? A Red vinyl tape B Purple vinyl tape C Red placard with white letters D Purple placard with white letters Turkey Point ILC 25 Question 57 In accordance with O-ADM-209, Equipment Tagging and Labeling, how can post-accident instrumentation be identified? A Red vinyl tape B Purple vinyl tape C Red placard with white letters D Purple placard with white letters

Turkey Point ILC 25 Question 58 Initial conditions: Unit 3 is in Mode 5. 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: H 114, PRMS HI RADIATION, alarms due to PRMS-R-3-11, Particulate Radiation Monitor. In accordance with 3-NOP-053, what is the effect of the R-ll alarm? A Both fans will trip. Containment isolation is achieved when the purge isolation valves close. B Both fans will trip. Containment isolation is achieved if one purge isolation valve fails to close. C Only 3V9 will trip. Containment isolation is achieved by the purge isolation valves. D Only 3V9 will trip. 4V20 must be stopped to achieve Containment isolation. Turkey Point ILC 25 Question 58 Initial conditions: Unit 3 is in Mode 5. 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: H 114, PRMS HI RADIATION, alarms due to PRMS-R-3-11, Particulate Radiation Monitor. In accordance with 3-NOP-053, what is the effect of the R-ll alarm? A Both fans will trip. Containment isolation is achieved when the purge isolation valves close. B Both fans will trip. Containment isolation is achieved if one purge isolation valve fails to close. COnly 3V9 will trip. Containment isolation is achieved by the purge isolation valves. D Only 3V9 will trip. 4V20 must be stopped to achieve Containment isolation.

Turkey Point ILC 25 Question 59 Spent Fuel Pit (SFP) boron is 2000 ppm HIll SFP LO LEVEL actuates In accordance with 3-0P-033, Spent Fuel Pit Cooling System, what is the preferred method of making up to the SFP for the above conditions? A Demin Water System B Primary Water Storage Tank C Refueling Water Storage Tank D CVCS Holdup Tanks Turkey Point ILC 25 Question 59 Spent Fuel Pit (SFP) boron is 2000 ppm H 111 SFP LO LEVEL actuates In accordance with 3-0P-033, Spent Fuel Pit Cooling System, what is the preferred method of making up to the SFP for the above conditions? A Demin Water System B Primary Water Storage Tank C Refueling Water Storage Tank D CVCS Holdup Tanks

Turkey Point ILC 25 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/Gs using the B Standby Steam Generator Feedpump. All wide range S/G 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. Main Feed flow indication is not accurate in the range required. B use change in Thots. Bypass Feed flow is not seen by the Main Feed flow transmitters. C establish less than 100 gpm flow to each S/G 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/G using AFW flow indication. Bypass Feed flow is not seen by the Main Feed flow transmitters. Turkey Point ILC 25 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/Gs using the B Standby Steam Generator Feedpump. All wide range S/G 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. Main Feed flow indication is not accurate in the range required. B use change in Thots. Bypass Feed flow is not seen by the Main Feed flow transmitters. C establish less than 100 gpm flow to each S/G 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/G using AFW flow indication. Bypass Feed flow is not seen by the Main Feed flow transmitters.

Turkey Point ILC 25 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. Tavg is 558°F. How will the Steam Dump to Condenser Valves operate based on the above conditions? 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. Turkey Point ILC 25 Question 61 Unit 3 is steady at 40% power. Turbine First Stage Pressure Transmitter PT 447 has just failed high. The turbine subsequently trips. Tavg is 558°F. How will the Steam Dump to Condenser Valves operate based on the above conditions? 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.

Turkey Point ILC 25 Question 62 Unit 3 is at 100% power when the steam jet air ejector common steam supply valve, 3-30-020, is inadvertently closed. Which one of the following describes the effect of closing valve 3-30-0207 A. Condenser vacuum will decrease Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease B. Condenser vacuum will decrease Main generator megawatts will decrease Turbine exhaust hood temperatures will increase C. Tavg will increase Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease D. Tavg will increase Main generator megawatts will increase Turbine exhaust hood temperatures will increase Turkey Point ILC 25 Question 62 Unit 3 is at 100% power when the steam jet air ejector common steam supply valve, 3-30-020, is inadvertently closed. Which one of the following describes the effect of closing valve 3-30-0207 A. Condenser vacuum will decrease Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease B. Condenser vacuum will decrease Main generator megawatts will decrease Turbine exhaust hood temperatures will increase C. Tavg will increase Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease D. Tavg will increase Main generator megawatts will increase Turbine exhaust hood temperatures will increase

Turkey Point ILC 25 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 Turkey Point ILC 25 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

Turkey Point ILC 25 Question 64 How will high alanns on RAD-6643, Control Room Ventilation Radiation Monitor, and R-12, Containment Air Radiation Monitor, impact Control Room Ventilation Isolation and Containment Ventilation Isolation? CR HV AC is Control Room Ventilation CVI is Containment Ventilation Isolation A RAD-6643 will actuate CR HV AC isolation and CVI. R-12 will actuate CVI and CR HVAC isolation. B RAD-6643 will actuate CR HV AC isolation only. R-12 will actuate CVI and CR HVAC isolation. C RAD-6643 will actuate CR HV AC isolation and CVI. R-12 will actuate CVI only. D RAD-6643 will actuate CR HV AC isolation only. R-12 will actuate CVI only. Turkey Point ILC 25 Question 64 How will high alarms on RAD-6643, Control Room Ventilation Radiation Monitor, and R-12, Containment Air Radiation Monitor, impact Control Room Ventilation Isolation and Containment Ventilation Isolation? CR HV AC is Control Room Ventilation CVI is Containment Ventilation Isolation A RAD-6643 will actuate CR HVAC isolation and CVI. R-12 will actuate CVI and CR HVAC isolation. B RAD-6643 will actuate CR HVAC isolation only. R-12 will actuate CVI and CR HVAC isolation. C RAD-6643 will actuate CR HVAC isolation and CVI. R-12 will actuate CVI only. D RAD-6643 will actuate CR HVAC isolation only. R-12 will actuate CVI only.

Turkey Point ILC 25 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. How will the ICW 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. COnly 3C ICW Pump will be stripped. 3A and 3B ICW Pumps will receive start signals from the Sequencers. D Only 3C ICW Pump will be stripped. 3A and 3C ICW Pumps will receive start signals from the Sequencers. Turkey Point ILC 25 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. How will the ICW 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. COnly 3C ICW Pump will be stripped. 3A and 3B ICW Pumps will receive start signals from the Sequencers. D Only 3C ICW Pump will be stripped. 3A and 3C ICW Pumps will receive start signals from the Sequencers.

Turkey Point ILC 25 Question 66 The Turbine Operator (TO) is performing valve lineups in accordance with 3-0P-081.1, F eedwater 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-100, 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 Turkey Point ILC 25 Question 66 The Turbine Operator (TO) is perfonning 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-100, 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

Turkey Point ILC 25 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. B Yes; two more assemblies may be sent over before 0800. C No; the cumulative average fuel transfer rate will be violated. D No; the number of assemblies moved in one hour will be violated. Turkey Point ILC 25 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. B Yes; two more assemblies may be sent over before 0800. C No; the cumulative average fuel transfer rate will be violated. D No; the number of assemblies moved in one hour will be violated.

Turkey Point ILC 25 Question 68 In accordance with O-ADM-503, Temporary System Alteration, which one of the following requires a Temporary System Alteration (TSA) for configuration control? A B C D Hose installed to direct flow from a drain line to a floor drain Cit'/' Cc)r7cft'/7'(;)~/ nlJ un/l ~ (T"/U//de Installing temporarH'entilation in the 4B MCC Room to maintain its temperature below design limits A temporary electrical heater plugged into a 120V outlet to maintain the Unit 3 Charging Pump Room above 65°F Bistables tripped in accordance with 3/4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for greater than one shift Turkey Point ILC 25 Question 68 In accordance with O-ADM-503, Temporary System Alteration, which one of the following requires a Temporary System Alteration (TSA) for configuration control? A B C D Hose installed to direct flow from a drain line to a floor drain cu'r' ct.)r'1?~'f,'cJr;/ n1 vrn// ~ vP/U////e.. Installing temporar~ventilation in the 4B MCC Room to maintain its temperature below design limits A temporary electrical heater plugged into a 120V outlet to maintain the Unit 3 Charging Pump Room above 65°F Bistables tripped in accordance with 3/4-0NOP-049.l, Deviation or Failure of Safety Related or Reactor Protection Channels, for greater than one shift

Turkey Point ILC 25 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 AS/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 AS/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 Turkey Point ILC 25 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 A S/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 A S/G Lock up Auto B S/G Lock up Lock up C S/G Lock up Auto

Turkey Point ILC 25 Question 70 A plant cooldown is in progress on Unit 4. RCS temperature is 290°F and lowering. RCS pressure is 370 psig and lowering. When 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 Turkey Point ILC 25 Question 70 A plant cooldown is in progress on Unit 4. RCS temperature is 290°F and lowering. RCS pressure is 370 psig and lowering. When 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 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

Turkey Point ILC 25 Question 71 A Waste Monitor Tank is to be released. In accordance with 0-OP-061.11, 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 Chemistry Technician will 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 Chemistry Technician 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. 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. Turkey Point ILC 25 Question 71 A Waste Monitor Tank is to be released. In accordance with 0-OP-061.11, 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 Chemistry Technician will 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 Chemistry Technician 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. 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.

Turkey Point ILC 25 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 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 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 15 minutes to complete the task. Each worker has 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 20 minutes to complete the task. The female has no dose and the male worker has 200 mrem for the year. Turkey Point ILC 25 Question 72 An OSP is to be performed in the Auxiliary Building. The general area dose rate is 100 mrem/hr. 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 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 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 15 minutes to complete the task. Each worker has 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 20 minutes to complete the task. The female has no dose and the male worker has 200 mrem for the year.

Turkey Point ILC 25 Question 73 Unit 3 is at 100% power. Power Range N-44 is out of service. All required actions have been taken in accordance with 3-0NOP-059.8, Power Range Nuclear Instrumentation Malfunction. For the above conditions, which one of the following conditions requires immediate entry into the EOP network? A Containment Isolation Phase A on Trains A and B B Loss of 120 VAC Panel3P09 C Channel 3 OP~T actuation D Loss of 120 V AC Panel 3P08 Turkey Point ILC 25 Question 73 Unit 3 is at 100% power. Power Range N -44 is out of service. All required actions have been taken in accordance with 3-0NOP-059.8, Power Range Nuclear Instrumentation Malfunction. For the above conditions, which one of the following conditions requires immediate entry into the EOP network? A Containment Isolation Phase A on Trains A and B B Loss of 120 VAC Panel 3P09 C Channel 3 OP6T actuation D Loss of 120 VAC Panel 3P08

Turkey Point ILC 25 Question 74 Unit 3 is operating at 100% power when the following alarms 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 DEVIATION ~ G 4/3, RCS METAL IMPACT ~ G 5/2, AXIAL FLUX ADMIN LIMIT EXCEEDED What action should the crew take based on the above alarms? A Transfer 1 st Stage Pressure Controller to operable channel B Place Pressurizer Pressure Controller in MANUAL C Place 3B FRV in MANUAL D Place rods in MANUAL Turkey Point ILC 25 Question 74 Unit 3 is operating at 100% power when the following alarms occur: );> A 9/2, PZR CONTROL HIILO PRESS );> B 6/3, POWER RANGE OVERPOWER ROD STOP );> B 6/4, POWER RANGE CHANNEL DEVIA nON );> 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 alarms? 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

Turkey Point ILC 25 Question 75 The Unit 4 reactor has tripped due to a faulted 4A S/G. SI has actuated. When should the BOP initially isolate AFW to the 4A S/G? A In 4-EOP-E-O, Reactor Trip or Safety Injection, during performance of the main body of the procedure. B In 4-EOP-E-O, 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. D In 4-EOP-E-2, Faulted Steam Generator Isolation, when the Fold Out Page is directed. Turkey Point ILC 25 Question 75 The Unit 4 reactor has tripped due to a faulted 4A S/G. SI has actuated. When should the BOP initially isolate AFW to the 4A S/G? A In 4-EOP-E-O, Reactor Trip or Safety Injection, during performance of the main body of the procedure. B In 4-EOP-E-O, 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. D In 4-EOP-E-2, Faulted Steam Generator Isolation, when the Fold Out Page is directed.

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ES-401 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: Facility/Unit: Turkey Point Units 3 & 4 Region: I D II X III U IV U Reactor Type: WXCEUSWUGEU Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final 9rade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion. Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results RO/SRO-OnlylTotal Examination Values / -- / -- Points Applicant's Scores / -- / -- Points Applicant's Grade / -- / -- Percent ES-401 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: Facility/Unit: Turkey Point Units 3 & 4 Region: I D II X III U IV U Reactor Type: WXCEUSWUGEU Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion. Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results RO/SRO-Only/Total Examination Values / -- / -- Points Applicant's Scores / -- / -- Points Applicant's Grade / -- / -- Percent

Turkey Point ILC 25 SROKEY 1 c 57 B 2 D 58 C 3 D 59 C 4 B 60 A 5 A 61 D 6 B 62 B 7 B 63 D 8 A 64 B 9 B 65 C 10 D 66 D 11 A 67 A 12 D 68 B 13 A 69 A 14 C 70 D 15 B 71 C 16 A 72 A 17 B 73 D 18 D 74 D 19 A 75 B 20 B 76 D 21 A 77 A 22 B 78 C 23 B 79 A 24 B 80 A 25 D 81 A 26 A 82 C 27 D 83 D 28 B 84 B 29 D 85 D 30 C 86 C 31 B 87 A 32 C 88 A 33 D 89 C 34 B 90 A 35 B 91 B 36 A 92 D 37 B 93 B 38 B 94 A 39 B 95 D 40 D 96 C 41 C 97 A 42 B 98 B 43 A 99 C 44 C 100 B 45 C 46 C 47 C 48 C 49 D 50 C 51 C 52 D 53 A 54 D 55 C 56 B Turkey Point ILC 25 SROKEY c 57 B 2 D 58 C 3 D 59 C 4 B 60 A 5 A 61 D 6 B 62 B 7 B 63 D 8 A 64 B 9 B 65 C 10 D 66 D II A 67 A 12 D 68 B 13 A 69 A 14 C 70 D IS B 71 C 16 A 72 A 17 B 73 D 18 D 74 D 19 A 75 B 20 B 76 D 21 A 77 A 22 B 78 C 23 B 79 A 24 B 80 A 25 D 81 A 26 A 82 C 27 D 83 D 28 B 84 B 29 D 85 D 30 C 86 C 31 B 87 A 32 C 88 A 33 D 89 C 34 B 90 A 35 B 91 B 36 A 92 D 37 B 93 B 38 B 94 A 39 B 95 D 40 D 96 C 41 C 97 A 42 B 98 B 43 A 99 C 44 C 100 B 45 C 46 C 47 C 48 C 49 D 50 C 51 C 52 D 53 A 54 D 55 C 56 B

Turkey Point ILC 25 Question 1 Unit 3 is at 100% power. Pressurizer pressure is decreasing. The bottom two rows of LEDs on the acoustic monitor are lit. The PORV tailpipe temperature is 220oP. The safety valve tailpipe temperatures are 130op. What can be determined by these indications? A The specific PORV that is leaking B The specific safety valve that is leaking C A PORV is leaking, but cannot determine which one D A safety valve is leaking, but cannot determine which one Turkey Point ILC 25 Question 1 Unit 3 is at 100% power. Pressurizer pressure is decreasing. The bottom two rows of LEDs on the acoustic monitor are lit. The PORV tailpipe temperature is 220°F. The safety valve tailpipe temperatures are 130°F. What can be determined by these indications? A The specific PORV that is leaking B The specific safety valve that is leaking C A PORV is leaking, but cannot determine which one D A safety valve is leaking, but cannot determine which one

Turkey Point ILC 25 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. MOV-4-843 A & B, HHSI to Cold Leg MOV, are both closed. RCS Subcooling is 40°F. For the given plant conditions, which one of the foHowing describes RCP operation in accordance with 4-EOP-E-l, and the basis for this action? 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. Turkey Point ILC 25 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. MOV-4-843 A & B, HHSI to Cold Leg MOV, are both closed. RCS Subcooling is 40°F. For the given plant conditions, which one of the following describes RCP operation in accordance with 4-EOP-E-l, and the basis for this action? 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.

Turkey Point ILC 25 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 with a negative 0.1 dpm SUR. 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. In accordance with 3-EOP-F-0, Critical Safety Function Status Trees, what is the color of the critical safety function the unit is in and what procedure will the crew implement first? The plant meets the conditions for alan __ (>.,..::1:..,<.) __ path. The crew will implement (2) first. (1) A Orange B Red C Orange D Red (2) 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS Turkey Point ILC 25 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 with a negative 0.1 dpm SUR. 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-O, Reactor Trip or Safety Injection. In accordance with 3-EOP-F-O, Critical Safety Function Status Trees, what is the color of the critical safety function the unit is in and what procedure will the crew implement first? The plant meets the conditions for alan __ (,-,1'-./..) __ path. The crew will implement (2) first. (1) A Orange B Red C Orange D Red (2) 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-P.l, Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS 3-EOP-FR-S.l, Response to Nuclear Power GenerationlATWS

Turkey Point ILC 25 Question 4 Unit 3 is at 35% power. The 3A RCP breaker has just tripped. Which one of the following statements correctly describes how the plant will respond and the reason a reactor trip is necessary? A The reactor will automatically trip to maintain DNBR within acceptable limits. B The reactor will NOT automatically trip. It must be manually tripped to maintain DNBR within acceptable limits C The reactor will automatically trip to maintain power density (kw/ft) within acceptable limits. D The reactor will NOT automatically trip. It must be manually tripped to maintain power density (kw/ft) within acceptable limits. Turkey Point ILC 25 Question 4 Unit 3 is at 35% power. The 3A RCP breaker has just tripped. Which one of the following statements correctly describes how the plant will respond and the reason a reactor trip is necessary? A The reactor will automatically trip to maintain DNBR within acceptable limits. B The reactor will NOT automatically trip. It must be manually tripped to maintain DNBR within acceptable limits C The reactor will automatically trip to maintain power density (kw/ft) within acceptable limits. D The reactor will NOT automatically trip. It must be manually tripped to maintain power density (kw/ft) within acceptable limits.

Turkey Point ILC 25 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: ~ FI-3-122, Charging Line Flow Indicator, indicates 10 gpm and decreasing ~ G 1/2, CHARGING PUMPS HI SPEED, is in alarm ~ A 9/3, PZR CONTROL HIILO LEVEL, is in alarm ~ VCT level is 25% and increasing ~ The SNPO reports abnormal noise coming from the 3A Charging Pump and it is vibrating. In accordance with 3-0NOP-047.1, Loss of Charging Flow in Modes 1 Through 4, which one of the following is the cause of the above event? The 3A Charging Pump... A is becoming gas bound. B controller has lost Instrument Air. C suction piping is leaking. D discharge piping is leaking. Turkey Point ILC 25 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: > FI-3-122, Charging Line Flow Indicator, indicates 10 gpm and decreasing > G 112, CHARGING PUMPS HI SPEED, is in alarm > A 9/3, PZR CONTROL HIILO LEVEL, is in alarm > VCT level is 25% and increasing > The SNPO reports abnormal noise coming from the 3A Charging Pump and it is vibrating. In accordance with 3-0NOP-04 7.1, Loss of Charging Flow in Modes 1 Through 4, which one of the following is the cause of the above event? The 3A Charging Pump... A is becoming gas bound. B controller has lost Instrument Air. C suction piping is leaking. D discharge piping is leaking.

Turkey Point ILC 25 Question 6 Initial conditions: Unit 4 operated for 2 effective full power 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 Note: 1.3483 (MWD/MTU)/EFPH A 40 to 45 minutes B 55 to 60 minutes C 85 to 90 minutes D 185 to 190 minutes Turkey Point ILC 25 Question 6 Initial conditions: Unit 4 operated for 2 effective full power 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 Note: 1.3483 (MWD/MTU)/EFPH A 40 to 45 minutes B 55 to 60 minutes C 85 to 90 minutes D 185 to 190 minutes

Turkey Point ILC 25 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 _-.l.(~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 run at min speed all Charging Pumps D run at min speed one Charging Pump Turkey Point ILC 25 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 Purop(s) be operated during this event? The 4A Charging Pump will be _--.l.(.=...,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 run at min speed all Charging Pumps D run at min speed one Charging Pump

Turkey Point ILC 25 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 respond within the first minute? Liquid space Vapor space A Increase Increase B Increase Decrease C Decrease Decrease D Decrease Increase Turkey Point ILC 25 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 respond within the first minute? Liquid space Vapor space A Increase Increase B Increase Decrease C Decrease Decrease D Decrease Increase

Turkey Point ILC 25 Question 9 Unit 4 has experienced a Steam Generator tube rupture. Off-site power has been lost and will not be restored for 24 hours. In accordance with 4-EOP-E-3, Steam Generator Tube Rupture, how will the RCS cooldown and depressurization to terminate safety injection be conducted? The crew will dump steam to (1) and depressurize the RCS using (2) (1) (2) A atmosphere auxiliary spray B atmosphere aPORV C the condenser auxiliary spray D the condenser aPORV Turkey Point ILC 25 Question 9 Unit 4 has experienced a Steam Generator tube rupture. Off-site power has been lost and will not be restored for 24 hours. In accordance with 4-EOP-E-3, Steam Generator Tube Rupture, how will the RCS cooldown and depressurization to terminate safety injection be conducted? The crew will dump steam to (1) and depressurize the RCS using (2) (1) (2) A atmosphere auxiliary spray B atmosphere aPORV C the condenser auxiliary spray D the condenser aPORV

Turkey Point ILC 25 Question 10 Unit 4 was initially at 100% power. A Feedline break developed to the 4A S/G inside Containment at the Containment penetration. 4A S/G pressure is 400 psig at the moment of S/G isolation. Which one of the following describes the effect of this event? A RCS temperatures lower prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. B RCS temperatures lower prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation. C RCS temperatures rise prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. D RCS temperatures rise prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation. Turkey Point ILC 25 Question 10 Unit 4 was initially at 100% power. A Feedline break developed to the 4A S/G inside Containment at the Containment penetration. 4A S/G pressure is 400 psig at the moment of S/G isolation. Which one of the following describes the effect of this event? A RCS temperatures lower prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. B RCS temperatures lower prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation. C RCS temperatures rise prior to reactor trip. 4A S/G pressure stabilizes at approximately 400 psig. D RCS temperatures rise prior to reactor trip. 4A S/G pressure continues to depressurize after S/G Isolation.

Turkey Point ILC 25 Question 11 Unit 3 has experienced a loss of all AC power. The crew has determined that a source of power is not available. In accordance with 3-EOP-ECA-O.O, Loss of All AC Power, why are RCP Seal Manual Isolation Valves (3-297 AlBIC) and the RCP Seal Cooling Water Outlet Valve (MOV 626) closed? 3-297 AlBIC are closed to prevent (1) (2) A (1) thermal 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) thermal shocking the RCPs D (1) thermal shocking the RCPs (2) thermal shocking the RCPs Turkey Point ILC 25 Question 11 Unit 3 has experienced a loss of all AC power. The crew has determined that a source of power is not available. In accordance with 3-EOP-ECA-O.O, Loss of All AC Power, why are RCP Seal Manual Isolation Valves (3-297 AlBIC) and the RCP Seal Cooling Water Outlet Valve (MOV 626) closed? 3-297 AlBIC are closed to prevent (1) (2) A (1) thermal 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) thermal shocking the RCPs D (1) thermal shocking the RCPs (2) thermal shocking the RCPs

Turkey Point ILC 25 Question 12 Unit 3 experienced a loss of offsite power. The 3A and 3B 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. B 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 ofthe level of safety of the plant. Turkey Point ILC 25 Question 12 Unit 3 experienced a loss of offsite power. The 3A and 3B 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. B 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.

Turkey Point ILC 25 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 Pane13P07. VCT level indicator LI-3-112 indicates 25%. VCT level indicator LI-3-115 indicates zero level. Annunciator A 4/6, VCT HIILO 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. Turkey Point ILC 25 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 Pane13P07. VCT level indicator LI-3-112 indicates 25%. VCT level indicator LI-3-115 indicates zero level. Annunciator A 4/6, VCT HIILO 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.

Turkey Point ILC 25 Question 14 Turkey Point has experienced a long-tenn total loss of Instrument Air. In accordance with O-ONOP-013, Loss ofInstrument Air, how is CV-3-2046A, 3A EDG Level Control Valve, opened to fill the 3A EDG day tank? CV-3-2046A 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 nonnallevel controller and a compressed nitrogen cylinder. Turkey Point ILC 25 Question 14 Turkey Point has experienced a long-tenn total loss of Instrument Air. In accordance with O-ONOP-OI3, Loss ofInstrument Air, how is CV-3-2046A, 3A EDG Level Control Valve, opened to fill the 3A EDG day tank? CV-3-2046A 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 nonnallevel controller and a compressed nitrogen cylinder.

Turkey Point ILC 25 Question 15 The crew is performing 3-EOP-ECA-1.2, LOCA outside Containment. In accordance with 3-EOP-ECA-1.2 which one of the following leak paths outside Containment will be isolated first? A SI Hot Leg Injection Valves B RHR Suction Valves C RHR Discharge to Cold Legs D SI to Cold Leg Isolation Valves Turkey Point ILC 25 Question 15 The crew is performing 3-EOP-ECA-1.2, LOCA outside Containment. In accordance with 3-EOP-ECA-1.2 which one of the following leak paths outside Containment will be isolated first? A SI Hot Leg Injection Valves B RHR Suction Valves C RHR Discharge to Cold Legs D SI to Cold Leg Isolation Valves

Turkey Point ILC 25 Question 16 Initial conditions: Unit 3 is in Mode 3. The 3B Steam Generator Feedpump not available. Subsequently: The Unit 3 Startup Transformer locks out. The Auxiliary Feedwater Pumps are not available. The Main Feedwater Pumps are not available. In accordance with 3-EOP-FR-H.l, 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 ASSGFP available B SSGFP NOT available D ASSGFP NOT available B SSGFP NOT available Turkey Point ILC 25 Question 16 Initial conditions: Unit 3 is in Mode 3. The 3B Steam Generator Feedpump not available. Subsequently: The Unit 3 Startup Transformer locks out. The Auxiliary Feedwater Pumps are not available. The Main Feedwater Pumps are 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 D ASSGFP NOT available B SSGFP NOT available

Turkey Point ILC 25 Question 17 Unit 3 has experienced a loss of emergency coolant recirculation. RWST level is 59,000 gallons. In accordance with 3-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation, what action will the crew take and why? 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 R WST 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 RWST. D only the Charging Pumps and Containment Spray Pumps. This will extend the availability of the RWST. Turkey Point ILC 25 Question 17 Unit 3 has experienced a loss of emergency coolant recirculation. RWST level is 59,000 gallons. In accordance with 3-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation, what action will the crew take and why? Immediatel y 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 RWST. D only the Charging Pumps and Containment Spray Pumps. This will extend the availability of the R WST.

Turkey Point ILC 25 Question 18 Unit 3 has experienced a reactor trip and safety injection. The crew has entered 3-EOP-E-2, Faulted Steam Generator Isolation. The 3A S/G is faulted and its wide range level is 8% and lowering. Which one of the following is correct? In accordance with E-2, the crew will stabilize _-,(1,..:1.,L.) __ temperatures using steam dumps. This is to minimize RCS (2) (1) (2) A cold leg cooldown B cold leg pressure Increase C hot leg cooldown D hot leg pressure Increase Turkey Point ILC 25 Question 18 Unit 3 has experienced a reactor trip and safety injection. The crew has entered 3-EOP-E-2, Faulted Steam Generator Isolation. The 3A S/G is faulted and its wide range level is 8% and lowering. Which one of the following is correct? In accordance with E-2, the crew will stabilize _---C('--"Ic,L) __ temperatures using steam dumps. This is to minimize RCS (2) (1) (2) A cold leg cooldown B cold leg pressure mcrease C hot leg cooldown D hot leg pressure mcrease

Turkey Point ILC 25 Question 19 Rod M-8 in Bank D Group 1 dropped into the core earlier. The crew is recovering rod M-8. Which lift coil disconnect switches will the crew place to disconnect in order to retrieve M-8 and why will the RO record the Bank D Group 1 step counter position? The crew will place the lift coil disconnect switches for (1) to the disconnect position (toggle switch down). The RO will record Bank D Group 1 step counter position as a reference point to (2) (1) (2) A all rods in Bank D except M-8 withdraw M-8 B all rods in Bank D except M-8 reset the pulse analog converter C only M-8 withdraw M-8 D onlyM-8 reset the pulse analog converter Turkey Point ILC 25 Question 19 Rod M-8 in Bank D Group 1 dropped into the core earlier. The crew is recovering rod M-8. Which lift coil disconnect switches will the crew place to disconnect in order to retrieve M-8 and why will the RO record the Bank D Group 1 step counter position? The crew will place the lift coil disconnect switches for (1) to the disconnect position (toggle switch down). The RO will record Bank D Group 1 step counter position as a reference point to (2) (1) (2) A all rods in Bank D except M-8 withdraw M-8 B all rods in Bank D except M-8 reset the pulse analog converter C only M-8 withdraw M-8 D only M-8 reset the pulse analog converter

Turkey Point ILC 25 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 without SI occurred 15 minutes ago and Tcolds have decreased to 530oP. Shutdown margin is not assured. B A reactor trip without SI 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. P L'lH could exceed design limits. Turkey Point ILC 25 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 without SI occurred 15 minutes ago and Tcolds have decreased to 530°F. Shutdown margin is not assured. B A reactor trip without SI 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.

Turkey Point ILC 25 Question 21 Initial conditions: Unit 4 is at 3 % power. All Pressurizer controls are in automatic. Subsequently I&C is performing 4-SMI -041.11, Pressurizer Level Protection Loops Quarterly Test. Pressurizer level control switch is in position 3. I&C placed Loop L-459 for LT-4-459 in the tripped condition. Concurrently, LT-4-461 fails high. How will the unit initially respond to the event? A Backup heaters will energize B The unit will trip C No immediate effect because LT-4-461 is selected for backup D No immediate effect because L T 459 is bypassed for testing Turkey Point ILC 25 Question 21 Initial conditions: Unit 4 is at 3% power. All Pressurizer controls are in automatic. Subsequently I&C is performing 4-SMI-041.11, Pressurizer Level Protection Loops Quarterly Test. Pressurizer level control switch is in position 3. I&C placed Loop L-459 for L T 459 in the tripped condition. Concurrently, LT-4-461 fails high. How will the unit initially respond to the event? A Backup heaters will energize B The unit will trip C No immediate effect because LT-4-461 is selected for backup D No immediate effect because LT 459 is bypassed for testing

Turkey Point ILC 25 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 high flux at shutdown alarm actuates, the Containment evacuation alarm (2).

0)

(2) A 32 cps must be manually actuated B 32 cps will automatically actuate C 50 cps must be manually actuated D 50 cps will automatically actuate Turkey Point ILC 25 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 high flux at shutdown alarm actuates, the Containment evacuation alarm (2).

0)

(2) A 32 cps must be manually actuated B 32 cps will automatically actuate C 50 cps must be manually actuated D 50 cps will automatically actuate

Turkey Point ILC 25 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 75% and slowly lowering.
RCV-OI8, Liquid Waste Discharge Valve, indicates as follows:

Red light - on Green light - on In accordance with 3-0NOP-067, Radioactive Effluent Release, which of the following is correct? A RCV -018 is open. Close RCV -018 from VPB with keyswitch. B RCV -018 is open. Close RCV -018 from the waste boron panel. C RCV-OI8 is closed. Flush R-I8 and re-initiate the release. D RCV-018 is closed. IfR-I8 alarm clears, re-initiate the release. Turkey Point ILC 25 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-18, Waste Disposal Liquid Effluent Monitor, high alarm is validated.
MT A level is 75% and slowly lowering.
RCV-018, Liquid Waste Discharge Valve, indicates as follows:

~ Red light - on ~ Green light - on In accordance with 3-0NOP-067, Radioactive Effluent Release, which of the following is correct? A RCV -018 is open. Close RCV -018 from VPB with keyswitch. B RCV -018 is open. Close RCV -018 from the waste boron panel. C RCV-018 is closed. Flush R-18 and re-initiate the release. D RCV -018 is closed. If R -18 alarm clears, re-initiate the release.

Turkey Point ILC 25 Question 24 In accordance with O-ONOP-I05, Control Room Evacuation, which of these actions is the Unit 3 RO expected to perform before leaving the Control Room? A Trip the reactor Close the MSIV s Verify RCPs running B Trip the reactor Trip the RCPs Close PORV block valves C Trip the Steam Generator Feedwater Pumps Close MSR Steam Stops Close PORV block valves D Trip the main turbine Close the MSIV s Start 3B Charging Pump Turkey Point ILC 25 Question 24 In accordance with O-ONOP-I05, Control Room Evacuation, which of these actions is the Unit 3 RO expected to perform before leaving the Control Room? A Trip the reactor Close the MSIV s Verify RCPs running B Trip the reactor Trip the RCPs Close PORV block valves C Trip the Steam Generator Feedwater Pumps Close MSR Steam Stops Close PORV block valves D Trip the main turbine Close the MSIVs Start 3B Charging Pump

Turkey Point ILC 25 Question 25 Initial Conditions: Unit 4 was at 100% power. 4A QSPDS has been declared inoperable because of aPT 404 failure. Subsequently: Unit 4 experienced a LOCA with Safety Injection. 50 gpm is indicated on FI-4-943, Safety Injection Flow. RWST level is also decreasing at 50 gpm. The crew entered 4-EOP-FR-C.2, Degraded Core Cooling. QSPDS Train B now indicates the following: Thots are all approximately 525°F. RCS subcooling is 126°F. Which of the following correctly describes QSPDS Train B indication and required action(s)? PT-I/-¢pt/(pr-t/-'!aP PC5 I/ot /.."9 f?~Stf~ '~/1Sh1lrk,..<: 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 approximately 2210 psig. Manually calculate subcooling. Turkey Point ILC 25 Question 25 Initial Conditions: 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. 50 gpm is indicated on FI-4-943, Safety Injection Flow. RWST level is also decreasing at 50 gpm. The crew entered 4-EOP-FR-C.2, Degraded Core Cooling. QSPDS Train B now indicates the following: Thots are all approximately 525°F. RCS subcooling is 126°F. Which of the following correctly describes QSPDS Train B indication and required action(s)? L? PT-q-~t./IPT-ij-,/OiP 2?G5 //01 /..#;) /r~S/F'~ '~rJ5h'7I//J."'<: 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 approximately 2210 psig. Manually calculate subcooling.

Turkey Point ILC 25 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 actuation 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 when Pressurizer pressure dropped below 1835 psig. 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. Turkey Point 1LC 25 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 actuation 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 HHS1 Pumps? The HHS1 Pumps are... A runmng. They auto started when Pressurizer pressure dropped below 1730 psig. B runnmg. They auto started when Pressurizer pressure dropped below 1835 psig. 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.

Turkey Point ILC 25 Question 27 A Containment purge was in progress on Unit 3. .* A LOCA occurred. The crew is responding to high containment radiation level. POV-3-2603, 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 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 VPA. D Fail POV-3-2603 closed by pulling its fuse behind VPB. Turkey Point ILC 25 Question 27 A Containment purge was in progress on Unit 3. A LOCA occurred. The crew is responding to high containment radiation level. POV-3-2603, 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 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 VPA. D Fail POV-3-2603 closed by pulling its fuse behind VPB.

Turkey Point ILC 25 Question 28 Safety Injection and Phase A have occurred on Unit 3. The Phase A signal has NOT been reset. Which one of the following states what effect this will have on RCP Number 1 seal leak off flow and why? Number 1 seal leak off flow will... A decrease because VCT pressure has increased. B decrease because the backpressure has increased. C go to and remain at zero because the RCP Seal Return to VCT is closed. D go to and remain at zero because #1 Seal LeakoffIsolation Valves are closed. Turkey Point ILC 25 Question 28 Safety Injection and Phase A have occurred on Unit 3. The Phase A signal has NOT been reset. Which one of the following states what effect this will have on RCP Number 1 seal leak off flow and why? Number 1 seal leak off flow wilL.. A decrease because VCT pressure has increased. B decrease because the backpressure has increased. C go to and remain at zero because the RCP Seal Return to VCT is closed. D go to and remain at zero because #1 Seal LeakoffIsolation Valves are closed.

Turkey Point ILC 25 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 ofthe following is the cause of the above conditions? A RV-3-382, Seal Return Relief Valve, leaking by B CV-3-303A, 3A RCP Seal LeakoffIsolation Valve failed closed C 3A Rep number 1 seal failure D 3A RCP number 2 seal failure Turkey Point ILC 25 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-Normal, which ofthe following is the cause of the above conditions? A RV-3-382, Seal Return Relief Valve, leaking by B CV-3-303A, 3A RCP Seal LeakoffIsolation Valve failed closed C 3A RCP number 1 seal failure D 3A RCP number 2 seal failure

Turkey Point ILC 25 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 Immediately trip the reactor and stop all RCPs B Bypass the RCP seal injection filters C Maintain CCW flow to the Rep thermal barriers D Shutdown the unit and stop all RCPs within 48 hours Turkey Point ILC 25 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 Immediately 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 48 hours

Turkey Point ILC 25 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--,-,O:..L) __. Flow to the core will (2) (1) (2) A decrease remain the same B decrease decrease C increase remain the same D increase decrease Turkey Point ILC 25 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;...L) __. Flow to the core will (2) (1) (2) A decrease remain the same B decrease decrease C mcrease remain the same D mcrease decrease

Turkey Point ILC 25 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 Turkey Point ILC 25 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

Turkey Point ILC 25 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 of the following identifies the operability of the 3A SI Accumulator and why? The 3A SI accumulator is... A OPERABLE. All Tech Spec limits are met. B INOPERABLE. The water level is out of specification. C INOPERABLE. The cover gas pressure is out of specification. D INOPERABLE. The boron concentration is out of specification. Turkey Point ILC 25 Question 33 Unit 3 is at 100% with the following 3A Safety Injection CSI) Accumulator values: ~ Level - 6560 gallons ~ Pressure - 670 psig ~ Boron concentration - 1925 ppm ~ The discharge MOV breaker is locked open Which of the following identifies the operability of the 3A SI Accumulator and why? The 3A SI accumulator is... A OPERABLE. All Tech Spec limits are met. B INOPERABLE. The water level is out of specification. C INOPERABLE. The cover gas pressure is out of specification. D INOPERABLE. The boron concentration is out of specification.

Turkey Point ILC 25 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 and is INOPERABLE. Based on the above conditions what is/are the MINIMUM action(s) required to be taken in accordance with Technical Specifications? A Restore PORV to OPERABLE status AND close the associated block valve with power maintained to the block valve. B Restore PORV to OPERABLE status OR close the associated block valve with power maintained to the block valve. C Restore PORV to OPERABLE status AND close the associated block valve with power removed to the block valve. D Restore PORV to OPERABLE status OR close the associated block valve with power removed to the block valve. Turkey Point ILC 25 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 and is INOPERABLE. Based on the above conditions what is/are the MINIMUM action(s) required to be taken in accordance with Technical Specifications? A Restore PORV to OPERABLE status AND close the associated block valve with power maintained to the block valve. B Restore PORV to OPERABLE status OR close the associated block valve with power maintained to the block valve. C Restore PORV to OPERABLE status AND close the associated block valve with power removed to the block valve. D Restore PORV to OPERABLE status OR close the associated block valve with power removed to the block valve.

Turkey Point ILC 25 Question 35 Which one of the following describes the operation of 3D 4kV bus feeder breakers 3AB19 and 3AD06? Note: 3AB19 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. 3AB 19 will remain closed if 3AD06 is opened. Turkey Point ILC 25 Question 35 Which one of the following describes the operation of 3D 4kV bus feeder breakers 3AB 19 and 3AD06? Note: 3AB19 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 if3AB19 is opened. D 3AD06 must be closed first. 3AB 19 will remain closed if 3AD06 is opened.

Turkey Point ILC 25 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 Turkey Point ILC 25 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

Turkey Point ILC 25 Question 37 What are the setpoints for the Pressurizer Backup Heaters energization (1) and Letdown isolation (2)? (1) PZR press of: (2)PZR level of: A 2210 psig 12% B 2210 psig 14% C 2220 psig 12% D 2220 psig 14% Turkey Point ILC 25 Question 37 What are the setpoints for the Pressurizer Backup Heaters energization (1) and Letdown isolation (2)? (1) PZR press of: (2)PZR level of: A 2210 psig 12% B 2210 psig 14% C 2220 psig 12% D 2220 psig 14%

Turkey Point ILC 25 Question 38 Initial conditions:

Unit is at 2% power.

J Train 4B RPS testing is in progress. /IIIf!:.; ttS! b.e'<I!?n The 4B Reactor Trip Bypass Breake1)B:;facked in and closed. '/1 Subsequently: 125V DC Bus 4DOl is lost. What is the status of the reactor trip breakers and will the reactor trip as a direct result of the 4DOl 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. Turkey Point ILC 25 Question 38 Initial conditions:

Unit is at 2% power.

1 Train 4B RPS testing is in progress. /IJII5.; tt5f b;Rlilfi?n The 4B Reactor Trip Bypass Breake1)87acked 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 4DOI 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.

Turkey Point ILC 25 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 will the crew implement? A 3-0NOP-003.6, Loss of 120V Vital Instrument Panel3P06 B 3-0NOP-003.7, Loss of 120V Vital Instrument Panel 3P07 C 3-0NOP-003.8, Loss of 120V Vital Instrument Pane13P08 D 3-0NOP-003.9, Loss of 120V Vital Instrument Panel3P09 Turkey Point ILC 25 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 will the crew implement? A 3-0NOP-003.6, Loss of 120V Vital Instrument Panel3P06 B 3-0NOP-003.7, Loss of 120V Vital Instrument Panel 3P07 C 3-0NOP-003.S, Loss of 120V Vital Instrument Panel3POS D 3-0NOP-003.9, Loss of 120V Vital Instrument Panel3P09

Turkey Poin! ILC 25 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' suction will be aligned 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 Turkey Poin! ILC 25 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' suction will be aligned 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

Turkey Point ILC 25 Question 41 Unit 3 has experienced a spurious safety injection. The RO has just commenced performance of 3-EOP-E-O, 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 D Three Four Turkey Point ILC 25 Question 41 Unit 3 has experienced a spurious safety injection. The RO has just commenced performance of 3-EOP-E-O, 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 D Three Four

Turkey Point ILC 25 Question 42 Initial conditions Unit 4 Containment temperature at 11 oop All Steam Generator narrow range levels on program at 60% Subsequently: CCW flow to the NCCs is lost Containment temperature has increased to 125°F All Steam Generator narrow range levels on program at 60% Steam Generator secondary system mass with the Containment at 125°P is (1) than at 11OoP. This is because the (2) leg density has decreased. (1) (2) A less variable B less reference C greater variable D greater reference Turkey Point ILC 25 Question 42 Initial conditions Unit 4 Containment temperature at 110°F All Steam Generator narrow range levels on pro gram at 60% Subsequently: CCW flow to the NCCs is lost Containment temperature has increased to 125°F All Steam Generator narrow range 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 D greater reference

Turkey Point ILC 25 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 880 A & B will NOT open. C The CSPs will NOT start. MOV 880 A & B will open. D The CSPs will NOT start. MOV 880 A & B will NOT open. Turkey Point ILC 25 Question 43 Unit 4 experienced a LOCA. The BOP is verifying Feedwater Isolation in accordance with 4-EOP-E-0, Attaclunent 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 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 880 A & B will open. D The CSPs will NOT start. MOV 880 A & B will NOT open.

Turkey Point ILC 25 Question 44 Initial conditions: Unit 3 is at 100% power. The RO has recently performed a dilution to compensate for fuel burnup. Subsequently, the following indications are noted in Control Room: Power Range NIs 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 stearn line leak Reduce power by reducing turbine load. D Main stearn line leak Reduce power by inserting control rods. Turkey Point ILC 25 Question 44 Initial conditions: Unit 3 is at 100% power. The RO has recently performed a dilution to compensate for fuel bumup. Subsequently, the following indications are noted in Control Room: Power Range NIs 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 by inserting control rods.

Turkey Point ILC 25 Question 45 Unit 3 was at 100% when 3P06 was lost. 3A S/G level is increasing slowly. The BOP is reducing feed to the 3A S/G when the following actuate: ~ Annunciator C 2/1, SG A NARROW RANGE HI LEVEL ~ Annunciator C 5/1, SG A STEAM> FEED ~ Bistable status light STM-FW FLOW DEV FC 478 B1 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 A reactor trip is NOT required. The BOP should continue reducing feed flow. B A reactor trip is NOT required. The BOP should stop reducing feed flow. C The RO should trip the reactor. SI is NOT required. D The RO should trip the reactor. SI is required. Turkey Point ILC 25 Question 45 Unit 3 was at 100% when 3P06 was lost. 3A S/G level is increasing slowly. The BOP is reducing feed to the 3A S/G when the following actuate: ~ Annunciator C 2/1, SG A NARROW RANGE HI LEVEL ~ Annunciator C 5/1, SG 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 Panel 3P06, how should the crew respond to the above event? A A reactor trip is NOT required. The BOP should continue reducing feed flow. B A reactor trip is NOT required. The BOP should stop reducing feed flow. C The RO should trip the reactor. SI is NOT required. D The RO should trip the reactor. SI is required.

Turkey Point ILC 25 Question 46 Unit 3 is at 100% power. The steam pressure input into the 3A S/O level control system fails high. Which of the following actions will occur? Initially, feedwater flow to the 3A S/O 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. Turkey Point ILC 25 Question 46 Unit 3 is at 100% power. The steam pressure input into the 3A S/O level control system fails high. Which of the following actions will occur? Initially, feedwater flow to the 3A S/O 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.

Turkey Point ILC 25 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. Turkey Point ILC 25 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.

Turkey Point ILC 25 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? 3A4kV Bus 3B 4kV Bus A Deenergized Deenergized B Deenergized Energized C Energized Deenergized D Energized Energized Turkey Point ILC 25 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 4kV Bus 3B 4kV Bus A Deenergized Deenergized B Deenergized Energized C Energized Deenergized D Energized Energized

Turkey Point ILC 25 Question 49 The PTN switchyard de energized. Only the 3B EDG started. The Unit 4 crew is performing 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? 4D01 4D23 A 2 hours 2 hours B 2 hours greater than 24 hours C greater than 24 hours 2 hours D greater than 24 hours greater than 24 hours Turkey Point ILC 25 Question 49 The PTN switchyard de energized. Only the 3B EDG started. The Unit 4 crew is performing 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? 4D01 4D23 A 2 hours 2 hours B 2 hours greater than 24 hours C greater than 24 hours 2 hours D greater than 24 hours greater than 24 hours

Turkey Point ILC 25 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 Turkey Point ILC 25 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

Turkey Point ILC 25 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. Turkey Point ILC 25 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.

Turkey Point ILC 25 Question 52 Chemistry reports an increase in gross equivalent iodine and 100lEbar activity. Based on the above report, complete the following. Process Radiation Monitor PRMS-3-20, Reactor Coolant Letdown Monitor, will display increased

0) due to increased (2)

0)

(2) A cpm Crud B cpm Fission products C mRlhr Crud D rnR/hr Fission products Turkey Point ILC 25 Question 52 Chemistry reports an increase in gross equivalent iodine and 100lEbar activity. Based on the above report, complete the following. Process Radiation Monitor PRMS-3-20, Reactor Coolant Letdown Monitor, will display increased

0) due to increased (2)

(1) (2) A cpm Crud B cpm Fission products C mR!hr Crud D mRJhr Fission products

Turkey Point ILC 25 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°P and stable. ~ Annunciator E 2/2, TURB BEARING HI TEMP, is in alarm. ~ Turbine bearing temperatures are 181 0p 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-Oll, Screen Wash System/Intake Malfunction. D Enter into Technical Specifications 3.0.3 and commence a reactor shutdown per 3-0NOP-IOO, Past Load Reduction. Turkey Point ILC 25 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 alarm. ~ 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-011, Screen Wash System/Intake Malfunction. C Increase cooling water flow to the turbine oil cooler and implement 3-0NOP-011, Screen Wash System/Intake Malfunction. D Enter into Technical Specifications 3.0.3 and commence a reactor shutdown per 3-0NOP-100, Fast Load Reduction.

Turkey Point ILC 25 Question 54 PTN has experienced a dual-unit loss of off-site power. -.-tf.t <;;'iA/1 kl'icvvi 1\\' The 3B EDG did not start. H<P- ~n.p;",,~ i 2. ~ What is the availability of the following air compressors? A 3CM, Unit 3 Instrument Air Motor Compressor, is available OCM!, Service Air Compressor, is available B 3CM, Unit 3 Instrument Air Motor Compressor, is available OCM!, Service Air Compressor, is NOT available C 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCM!, Service Air Compressor, is available D 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCM!, Service Air Compressor, is NOT available Turkey Point ILC 25 Question 54 PTN has experienced a dual-unit loss of off-site power. - ~ (' t.v J k.i '/(::v t?( 1\\<;;' The 3B EDG did not start. t?!-P- ~n.&""1" 2. ~ What is the availability of the following air compressors? A 3CM, Unit 3 Instrument Air Motor Compressor, is available OCMl, Service Air Compressor, is available B 3CM, Unit 3 Instrument Air Motor Compressor, is available OCMl, Service Air Compressor, is NOT available C 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCMl, Service Air Compressor, is available D 3CM, Unit 3 Instrument Air Motor Compressor, is NOT available OCMl, Service Air Compressor, is NOT available

Turkey Point ILC 25 Question 55 Unit 3 is in Mode 1. Containment temperature is 118°P. 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. Turkey Point ILC 25 Question 55 Unit 3 is in Mode 1. Containment temperature is 118°P. 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.

Turkey Point ILC 25 Question 56 HCV-4-121, Charging Flow to Regen Heat Exchanger Control Valve, is full open. How is the controller for HCV-4-121 adjusted to decrease charging line flow under normal conditions and how does HCV-4-121 fail on loss ofInstrument Air? The demand on the controller for HCV-4-121 is (1) to decrease charging line flow. HCV-4-121 fails (2) on loss ofInstrument Air. (1) (2) A decreased from 100% Open B increased from 0% Open C decreased from 100% Closed D increased from 0% Closed Turkey Point ILC 25 Question 56 HCV-4-121, Charging Flow to Regen Heat Exchanger Control Valve, is full open. How is the controller for HCV-4-121 adjusted to decrease charging line flow under normal conditions and how does HCV 121 fail on loss of Instrument Air? The demand on the controller for HCV-4-121 is (1) to decrease charging line flow. HCV-4-121 fails (2) on loss ofInstrument Air. (1) (2) A decreased from 100% Open B increased from 0% Open C decreased from 100% Closed D increased from 0% Closed

Turkey Point ILC 25 Question 57 In accordance with O-ADM-209, Equipment Tagging and Labeling, how can post-accident instrumentation be identified? A Red vinyl tape B Purple vinyl tape C Red placard with white letters D Purple placard with white letters Turkey Point ILC 25 Question 57 In accordance with O-ADM-209, Equipment Tagging and Labeling, how can post-accident instrumentation be identified? A Red vinyl tape B Purple vinyl tape C Red placard with white letters D Purple placard with white letters

Turkey Point ILC 25 Question 58 Initial conditions: Unit 3 is in Mode 5. 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: H 114, PRMS HI RADIATION, alarms due to PRMS-R-3-11, Particulate Radiation Monitor. In accordance with 3-NOP-053, what is the effect of the R-l1 alarm? A Both fans will trip. Containment isolation is achieved when the purge isolation valves close. B Both fans will trip. Containment isolation is achieved if one purge isolation valve fails to close. COnly 3V9 will trip. Containment isolation is achieved by the purge isolation valves. D Only 3V9 will trip. 4V20 must be stopped to achieve Containment isolation. Turkey Point ILC 25 Question 58 Initial conditions: Unit 3 is in Mode 5. 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: H 114, PRMS HI RADIATION, alarms due to PRMS-R-3-11, Particulate Radiation Monitor. In accordance with 3-NOP-053, what is the effect of the R-ll alarm? A Both fans will trip. Containment isolation is achieved when the purge isolation valves close. B Both fans will trip. Containment isolation is achieved if one purge isolation valve fails to close, C Only 3V9 will trip, Containment isolation is achieved by the purge isolation valves. D Only 3V9 will trip. 4V20 must be stopped to achieve Containment isolation,

Turkey Point ILC 25 Question 59 Spent Fuel Pit (SFP) boron is 2000 ppm H 111 SFP LO LEVEL actuates In accordance with 3-0P-033, Spent Fuel Pit Cooling System, what is the preferred method of making up to the SFP for the above conditions? A Demin Water System B Primary Water Storage Tank C Refueling Water Storage Tank D CVCS Holdup Tanks Turkey Point ILC 25 Question 59 Spent Fuel Pit (SFP) boron is 2000 ppm H 111 SFP LO LEVEL actuates In accordance with 3-0P-033, Spent Fuel Pit Cooling System, what is the preferred method of making up to the SFP for the above conditions? A Demin Water System B Primary Water Storage Tank C Refueling Water Storage Tank D CVCS Holdup Tanks

Turkey Point ILC 25 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/Gs using the B Standby Steam Generator Feedpump. All wide range S/G 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. Main Feed flow indication is not accurate in the range required. B use change in Thots. Bypass Feed flow is not seen by the Main Feed flow transmitters. C establish less than 100 gpm flow to each S/G 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/G using AFW flow indication. Bypass Feed flow is not seen by the Main Feed flow transmitters. Turkey Point ILC 25 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/Gs using the B Standby Steam Generator Feedpump. All wide range S/G 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. Main Feed flow indication is not accurate in the range required. B use change in Thots. Bypass Feed flow is not seen by the Main Feed flow transmitters. C establish less than 100 gpm flow to each S/G 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/G using AFW flow indication. Bypass Feed flow is not seen by the Main Feed flow transmitters.

Turkey Point ILC 25 Question 61 Unit 3 is steady at 40% power. Turbine First Stage Pressure Transmitter PT 447 has just failed high. The turbine subsequently trips. Tavg is 558°F. How will the Steam Dump to Condenser Valves operate based on the above conditions? 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. Turkey Point ILC 25 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. Tavg is 558°F. How will the Steam Dump to Condenser Valves operate based on the above conditions? 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.

Turkey Point ILC 25 Question 62 Unit 3 is at 100% power when the steam jet air ejector common steam supply valve, 3-30-020, is inadvertently closed. Which one of the following describes the effect of closing valve 3-30-020? A. Condenser vacuum will decrease Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease B. Condenser vacuum will decrease Main generator megawatts will decrease Turbine exhaust hood temperatures will increase C. Tavg will increase Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease D. Tavg will increase Main generator megawatts will increase Turbine exhaust hood temperatures will increase Turkey Point ILC 25 Question 62 Unit 3 is at 100% power when the steam jet air ejector common steam supply valve, 3-30-020, is inadvertently closed. Which one of the following describes the effect of closing valve 3-30-0207 A. Condenser vacuum will decrease Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease B. Condenser vacuum will decrease Main generator megawatts will decrease Turbine exhaust hood temperatures will increase C. Tavg will increase Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease D. Tavg will increase Main generator megawatts will increase Turbine exhaust hood temperatures will increase

Turkey Point ILC 25 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 Turkey Point ILC 25 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

Turkey Point ILC 25 Question 64 How will high alarms on RAD-6643, Control Room Ventilation Radiation Monitor, and R-12, Containment Air Radiation Monitor, impact Control Room Ventilation Isolation and Containment Ventilation Isolation? CR HV AC is Control Room Ventilation CVI is Containment Ventilation Isolation A RAD-6643 will actuate CR HV AC isolation and CVI. R-12 will actuate CVI and CR HVAC isolation. B RAD-6643 will actuate CR HV AC isolation only. R-12 will actuate CVI and CR HVAC isolation. C RAD-6643 will actuate CR HVAC isolation and CVI. R-12 will actuate CVI only. D RAD-6643 will actuate CR HV AC isolation only. R-12 will actuate CVI only. Turkey Point ILC 25 Question 64 How will high alarms on RAD-6643, Control Room Ventilation Radiation Monitor, and R-12, Containment Air Radiation Monitor, impact Control Room Ventilation Isolation and Containment Ventilation Isolation? CR HV AC is Control Room Ventilation CVI is Containment Ventilation Isolation A RAD-6643 will actuate CR HV AC isolation and CVI. R-12 will actuate CVI and CR HVAC isolation. B RAD-6643 will actuate CR HV AC isolation only. R-12 will actuate CVI and CR HVAC isolation. C RAD-6643 will actuate CR HVAC isolation and CVI. R-12 will actuate CVI only. D RAD-6643 will actuate CR HV AC isolation only. R-12 will actuate CVI only.

Turkey Point ILC 25 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. How will the ICW 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. COnly 3C ICW Pump will be stripped. 3A and 3B ICW Pumps will receive start signals from the Sequencers. D Only 3C ICW Pump will be stripped. 3A and 3C ICW Pumps will receive start signals from the Sequencers. Turkey Point ILC 25 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. How will the ICW 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. COnly 3C ICW Pump will be stripped. 3A and 3B ICW Pumps will receive start signals from the Sequencers. D Only 3C ICW Pump will be stripped. 3A and 3C ICW Pumps will receive start signals from the Sequencers.

Turkey Point ILC 25 Question 66 The Turbine Operator (TO) is performing valve lineups in accordance with 3-0P-OSl.l, F eedwater Heaters, Extraction Steam Vents, and Drains Valve Alignment. The TO has performed the initial OTSC check for 3-0P-OSl.1. Complete the following: In accordance with 0-ADM-100, 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 S Document Control Hard Copy Index B S Lotus Notes C 24 Document Control Hard Copy Index D 24 Lotus Notes Turkey Point ILC 25 Question 66 The Turbine Operator (TO) is performing valve lineups in accordance with 3-0P-081.1, F eedwater 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-100, 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

Turkey Point ILC 25 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. B Yes; two more assemblies may be sent over before 0800. C No; the cumulative average fuel transfer rate will be violated. D No; the number of assemblies moved in one hour will be violated. Turkey Point ILC 25 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. B Yes; two more assemblies may be sent over before 0800. C No; the cumulative average fuel transfer rate will be violated. D No; the number of assemblies moved in one hour will be violated.

Turkey Point ILC 25 Question 68 In accordance with O-ADM-503, Temporary System Alteration, which one of the following requires a Temporary System Alteration (TSA) for configuration control? A B C D Hose installed to direct flow from a drain line to a floor drain ?tl'/' c.o~,,;,'cJ,?/ n/j t1n)/ k> //J:V/de Installing temporarRentilation in the 4B MCC Room to maintain its temperature below design limits A temporary electrical heater plugged into a 120V outlet to maintain the Unit 3 Charging Pump Room above 65°F Bistables tripped in accordance with 3/4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for greater than one shift Turkey Point ILC 25 Question 68 In accordance with O-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 Ct/r Cor7tit'f,'c;r,/ n/j tU7)1 b ~/U//de B Installing temporarB'entilation 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 Bistables tripped in accordance with 3/4-0NOP-049.l, Deviation or Failure of Safety Related or Reactor Protection Channels, for greater than one shift

Turkey Point ILC 25 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 AS/G Lockup Auto B S/G Auto Auto C S/G Manual Manual B AS/G Auto Lockup B S/G Auto Auto C S/G Manual Manual C AS/G Auto Lock up B S/G Lockup Lock up C S/G Auto Lockup D AS/G Lock up Auto B S/G Lock up Lock up C S/G Lock up Auto Turkey Point ILC 25 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 AS/G Lock up Auto B S/G Auto Auto C S/G Manual Manual B A S/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 A S/G Lock up Auto B S/G Lock up Lock up C S/G Lock up Auto

Turkey Point ILC 25 Question 70 A plant cooldown is in progress on Unit 4. RCS temperature is 290°F and lowering. RCS pressure is 370 psig and lowering. When 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 ofthe 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 Turkey Point ILC 25 Question 70 A plant cooldown is in progress on Unit 4. RCS temperature is 290°F and lowering. RCS pressure is 370 psig and lowering. When the OMS switches are placed in LO PRESS OPS the following alarm is received: ~ A 3/1, 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

Turkey Point ILC 25 Question 71 A Waste Monitor Tank is to be released. In accordance with O-OP-061.11, 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 Chemistry Technician will 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 Chemistry Technician will set the High and Warning values for PRMS-R-18. RCV-OI8, 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-OI8, Liquid Waste Discharge Valve, will control the flow rate at a value set by the SNPO. Turkey Point ILC 25 Question 71 A Waste Monitor Tank is to be released. In accordance with 0-OP-061.11, 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 Chemistry Technician will 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 Chemistry Technician 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. 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.

Turkey Point ILC 25 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 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 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 15 minutes to complete the task. Each worker has 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 20 minutes to complete the task. The female has no dose and the male worker has 200 mrem for the year. Turkey Point ILC 25 Question 72 An OSP is to be performed in the Auxiliary Building. The general area dose rate is 100 mrem/hr. 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 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 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 15 minutes to complete the task. Each worker has 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 20 minutes to complete the task. The female has no dose and the male worker has 200 mrem for the year.

Turkey Point ILC 25 Question 73 Unit 3 is at 100% power. Power Range N-44 is out of service. All required actions have been taken in accordance with 3-0NOP-059.8, Power Range Nuclear Instrumentation Malfunction. For the above conditions, which one of the following conditions requires immediate entry into the EOP network? A Containment Isolation Phase A on Trains A and B B

Loss of 120 VAC Pane13P09 C

Channel 3 OP ~ T actuation D Loss of 120 V AC Panel 3P08 Turkey Point ILC 25 Question 73 Unit 3 is at 100% power. Power Range N-44 is out of service. All required actions have been taken in accordance with 3-0NOP-059.S, Power Range Nuclear Instrumentation Malfunction. For the above conditions, which one ofthe following conditions requires immediate entry into the EOP network? A Containment Isolation Phase A on Trains A and B B

Loss of 120 VAC Panel3P09 C

Channel 3 OP~T actuation D Loss of 120 VAC Panel 3POS

Turkey Point ILC 25 Question 74 Unit 3 is operating at 100% power when the following alarms 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 DEVIATION ~ G 4/3, RCS METAL IMPACT ~ G 5/2, AXIAL FLUX ADMIN LIMIT EXCEEDED What action should the crew take based-on the above alarms? A Transfer 1st Stage Pressure Controller to operable channel B Place Pressurizer Pressure Controller in MANUAL C Place 3B FRV in MANUAL D Place rods in MANUAL Turkey Point ILC 25 Question 74 Unit 3 is operating at 100% power when the following alarms 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 DEVIATION G4/3,RCSMETALIMPACT G 5/2, AXIAL FLUX ADMIN LIMIT EXCEEDED What action should the crew take based on the above alarms? A Transfer 1 st Stage Pressure Controller to operable channel B Place Pressurizer Pressure Controller in MANUAL C Place 3B FRV in MANUAL D Place rods in MANUAL

Turkey Point ILC 25 Question 75 The Unit 4 reactor has tripped due to a faulted 4A S/G. SI has actuated. When should the BOP initially isolate AFW to the 4A S/G? A In 4-EOP-E-O, Reactor Trip or Safety Injection, during performance of the main body of the procedure. B In 4-EOP-E-O, 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. D In 4-EOP-E-2, Faulted Steam Generator Isolation, when the Fold Out Page is directed. Turkey Point ILC 25 Question 75 The Unit 4 reactor has tripped due to a faulted 4A S/G. SI has actuated. When should the BOP initially isolate AFW to the 4A S/G? A In 4-EOP-E-O, Reactor Trip or Safety Injection, during performance of the main body of the procedure. B In 4-EOP-E-O, 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. D In 4-EOP-E-2, Faulted Steam Generator Isolation, when the Fold Out Page is directed.

Turkey Point ILC 25 Question 76 Unit 4 was shutting down due to RCS leakage at 15 gpm. The reactor tripped during the shutdown. Off-site power was lost. All equipment operated as designed. The crew has entered 4-EOP-ES-O.l, Reactor Trip Response. In accordance with O-EPIP-20101, Duties of Emergency Coordinator, what are the Emergency Action Level Classifications for the RCS leakage and the loss of off-site power (LOOP)? RCS leakage LOOP A Alert Alert B Alert Unusual Event C Unusual Event Alert D Unusual Event Unusual Event Turkey Point ILC 25 Question 76 Unit 4 was shutting down due to RCS leakage at 15 gpm. The reactor tripped during the shutdown. Off-site power was lost. All equipment operated as designed. The crew has entered 4-EOP-ES-O.l, Reactor Trip Response. In accordance with O-EPIP-20101, Duties of Emergency Coordinator, what are the Emergency Action Level Classifications for the RCS leakage and the loss of off-site power (LOOP)? RCS leakage LOOP A Alert Alert B Alert Unusual Event C Unusual Event Alert D Unusual Event Unusual Event

Turkey Point ILC 25 Question 77 A Containment purge is in progress on Unit 3. Unit 3 experienced a small break LOCA with the following conditions: >> Safety Injection actuated. >> Containment pressure peaked at 15 psig. >> PRMS-R-14, Plant Vent Gas Monitor, and the Plant Vent SPING read pre-event values throughout the event. >> The position indicating lights for Containment Purge Exhaust Isolation Valve POV 2603 are not lit. >> Containment Purge Exhaust Isolation Valve POV-3-2602 indicates open. >> After 1 0 minutes the RO manually closed POV 2602. >> HHSI flow rate is 500 gpm. When filling out the Florida Nuclear Plant Emergency Notification Form, which box should the Shift Manager, acting as the Emergency Coordinator, check for "Release Status" and what is the classification? Release Classification A None Site Area Emergency B Has occurred, but stopped Alert C None Alert D Has occurred, but stopped Site Area Emergency Turkey Point ILC 25 Question 77 A Containment purge is in progress on Unit 3. Unit 3 experienced a small break LOCA with the following conditions: ~ Safety Injection actuated. ~ Containment pressure peaked at 15 psig. ~ PRMS-R-14, Plant Vent Gas Monitor, and the Plant Vent SPING read pre-event values throughout the event. ~ The position indicating lights for Containment Purge Exhaust Isolation Valve POV 2603 are not lit. ~ Containment Purge Exhaust Isolation Valve POV-3-2602 indicates open. ~ After 10 minutes the RO manually closed POV-3-2602. ~ HHSI flow rate is 500 gpm. When filling out the Florida Nuclear Plant Emergency Notification Form, which box should the Shift Manager, acting as the Emergency Coordinator, check for "Release Status" and what is the classification? Release Classification A None Site Area Emergency B Has occurred, but stopped Alert C None Alert D Has occurred, but stopped Site Area Emergency

Turkey Point ILC 25 Question 78 Unit 3 is at 100% power. Only the 3A Charging Pump is running. Letdown flow, temperature and pressure are fluctuating. The following alarms are alarming intermittently: ~ A 5/4, CVCS HP LTDN LINE HI TEMP ~ A 5/5, CVCS HP LTDN LINE HI FLOW / PRESS FI-3-122A, Charging Line Flow Indicator, indicates 70 gpm. The following alarms are in: ~ A 6/5, RCP LABYRINTH SEAL LO tlP ~ G 1/2, CHARGING PUMP HI SPEED Based on the above indications, where is the leak and which of the following mitigating strategies will be used if the leak can NOT be isolated? Note 3-0NOP-041.3, Excessive Reactor Coolant System Leakage 3-0NOP-047.1, Loss of Charging Flow in Modes 1 through 4 3-GOP-103, Power Operation to Hot Standby 3-EOP-E-0, Reactor Trip or Safety Injection leak location A Letdown line B Letdown line C Charging line D Charging line mitigating strategy enter 3-0NOP-041.3, trip the reactor, and go to 3-EOP-E-0 enter 3-0NOP-041.3 and commence a plant shutdown in accordance with 3-GOP-I03 enter 3-0NOP-047.1, trip the reactor, and go to 3-EOP-E-0 enter 3-0NOP-047.1 and commence a plant shutdown in accordance with 3-GOP-l 03 Turkey Point ILC 25 Question 78 Unit 3 is at 100% power. Only the 3A Charging Pump is running. Letdown flow, temperature and pressure are fluctuating. The following alarms are alarming intermittently: ~ A 5/4, CVCS HP L TDN LINE HI TEMP ~ A 5/5, CVCS HP LTDN LINE HI FLOW / PRESS FI-3-122A, Charging Line Flow Indicator, indicates 70 gpm. The following alarms are in: ~ A 6/5, RCP LABYRINTH SEAL LO ~P ~ G 1/2, CHARGING PUMP HI SPEED Based on the above indications, where is the leak and which ofthe following mitigating strategies will be used ifthe leak can NOT be isolated? Note 3-0NOP-041.3, Excessive Reactor Coolant System Leakage 3-0NOP-047.1, Loss of Charging Flow in Modes 1 through 4 3-GOP-I03, Power Operation to Hot Standby 3-EOP-E-0, Reactor Trip or Safety Injection leak location A Letdown line B Letdown line C Charging line D Charging line mitigating strategy enter 3-0NOP-041.3, trip the reactor, and go to 3-EOP-E-0 enter 3-0NOP-041.3 and commence a plant shutdown in accordance with 3-GOP-I03 enter 3-0NOP-047.1, trip the reactor, and go to 3-EOP-E-0 enter 3-0NOP-047.1 and commence a plant shutdown in accordance with 3-GOP-1 03

Turkey Point ILC 25 Question 79 Unit 3 has lost power to Vital Instrument Panel 3P06. The crew has entered 3-0NOP-003.6, Loss of 120V Vital Instrument PaneI3P06. LCV-3-115B, RWST to Charging Pump Suction, indicates open. VCT level on LI-3-115 is 17% and decreasing. Reactor power has not changed What is preventing flow through LCV 115B, and what is the maximum time for the crew to restore power to 3P06 before a unit shutdown must commence? (1) is holding RWST to Charging Pump Check Valve 3-357 closed. In accordance with Tech Specs, the crew has (2) to restore 3P06 or a unit shutdown must commence: (1) (2) A VCT pressure one hour B VCT pressure two hours C Blended flow one hour D Blended flow two hours Turkey Point ILC 25 Question 79 Unit 3 has lost power to Vital Instrument Panel 3P06. The crew has entered 3-0NOP-003.6, Loss of 120V Vital Instrument Panel 3P06. LCV-3-115B, RWST to Charging Pump Suction, indicates open. VCT level on LI-3-115 is 17% and decreasing. Reactor power has not changed What is preventing flow through LCV-3-115B, and what is the maximum time for the crew to restore power to 3P06 before a unit shutdown must commence? --'-'0'-.1.) __ is holding RWST to Charging Pump Check Valve 3-357 closed. In accordance with Tech Specs, the crew has (2) to restore 3P06 or a unit shutdown must commence:

0)

(2) A V CT pressure one hour B V CT pressure two hours C Blended flow one hour D Blended flow two hours

Turkey Point ILC 25 Question 80 The crew is performing 4-EOP-ES-1.3, Transfer to Cold Leg Recirculation. MOV-4-749A & B, RHR Heat Exchanger CCW Outlet Valves, are open. The Containment Recirculation Sump level is 435 inches. RWST level is 65,000 gallons. The RO has just started the 4A RHR Pump. The RHR flow and 4A RHR Pump amps are oscillating. What is causing the RHR flow and Pump amps to oscillate and what actions should the Unit Supervisor take in accordance with 4-EOP-ES-1.3, Transfer to Cold Leg Recirculation? A Both Recirculation Sump Screens are blocked. Transition to 4-EOP-ECA-l.l, Loss of Emergency Coolant Recirculation. B Both Recirculation Sump Screens are blocked. Continue in 4-EOP-ES-l.3 and direct the RO to start the 4B RHR Pump. C The Containment Recirculation Sump level is too low. Transition to 4-EOP-ECA-l.l, Loss of Emergency Coolant Recirculation. D The Containment Recirculation Sump level is too low. Continue in 4-EOP-ES-1.3 until the Sump level is within specifications. Turkey Point ILC 25 Question 80 The crew is performing 4-EOP-ES-1.3, Transfer to Cold Leg Recirculation. MOV-4-749A & B, RHR Heat Exchanger CCW Outlet Valves, are open. The Containment Recirculation Sump level is 435 inches. RWST level is 65,000 gallons. The RO has just started the 4A RHR Pump. The RHR flow and 4A RHR Pump amps are oscillating. What is causing the RHR flow and Pump amps to oscillate and what actions should the Unit Supervisor take in accordance with 4-EOP-ES-1.3, Transfer to Cold Leg Recirculation? A Both Recirculation Sump Screens are blocked. Transition to 4-EOP-ECA-l.l, Loss of Emergency Coolant Recirculation. B Both Recirculation Sump Screens are blocked. Continue in 4-EOP-ES-1.3 and direct the RO to start the 4B RHR Pump. C The Containment Recirculation Sump level is too low. Transition to 4-EOP-ECA-l.l, Loss of Emergency Coolant Recirculation. D The Containment Recirculation Sump level is too low. Continue in 4-EOP-ES-1.3 until the Sump level is within specifications.

Turkey Point ILC 25 Question 81 The 3A S/G has faulted and ruptured inside Containment. The crew is performing 3-EOP-E-2, Faulted Stearn Generator Isolation. The crew has been unable to manually isolate AFW to the 3A S/G. Alarm H 6/5, RWST LO LEVEL, has actuated. Containment sump level is 420" and rising. In accordance with 3-ARP-097.CR, Control Room Annunciator Response, what is the setpoint for alarm H 6/5 and what action will the Unit Supervisor direct for the above event? The setpoint for H 6/5 is _--->..(1=-.1.) __ gallons in the RWST. The Unit Supervisor will direct the crew to (2) NOTE: 3-EOP-ES-1.3, Transfer to Cold Leg Recirculation 3-EOP-E-3, Stearn Generator Tube Rupture (1) (2) A 155,000 stop performance of E-2 and go to ES-1.3 B 155,000 complete E-2 then go to ES-1.3 C 150,000 stop performance ofE-2 and go to ES-1.3 D 150,000 complete E-2 then go to ES-1.3 Turkey Point ILC 25 Question 81 The 3A S/G has faulted and ruptured inside Containment. The crew is performing 3-EOP-E-2, Faulted Steam Generator Isolation. The crew has been unable to manually isolate AFW to the 3A S/G. Alarm H 6/5, RWST LO LEVEL, has actuated. Containment sump level is 420" and rising. In accordance with 3-ARP-097.CR, Control Room Annunciator Response, what is the setpoint for alarm H 6/5 and what action will the Unit Supervisor direct for the above event? The setpoint for H 6/5 is _--,-,(1"-./.) __ gallons in the R WST. The Unit Supervisor will direct the crew to (2) NOTE: 3-EOP-ES-l.3, Transfer to Cold Leg Recirculation 3-EOP-E-3, Steam Generator Tube Rupture (1) (2) A 155,000 stop performance of E-2 and go to ES-l.3 B 155,000 complete E-2 then go to ES-l.3 C 150,000 stop performance ofE-2 and go to ES-1.3 D 150,000 complete E-2 then go to ES-l.3

Turkey Point ILC 25 Question 82 Unit 3 is operating at 100% power when the following occurs: Reactor power drops to 92% then returns to 99%. Tavg stabilizes 8°P lower. Pressurizer pressure drops to 2180 psig and is increasing slowly. Individual Rod Position Indication for rod M-8 indicates o. Which one of the following states the procedure that will be entered and an action that will be performed? A 3-0NOP-028, Reactor Control System Malfunction Verify shutdown margin is satisfied within one hour. B 3-0NOP-028, Reactor Control System Malfunction Reduce power to less than 90% within 30 minutes. C 3-0NOP-28.3, Dropped RCC Perform QPTR hourly until less than 50% power. D 3-0NOP-28.3, Dropped RCC Reduce Power Range Hi Plux Trip setpoint to 75% within one hour. Turkey Point ILC 25 Question 82 Unit 3 is operating at 100% power when the following occurs: Reactor power drops to 92% then returns to 99%. Tavg stabilizes 8°F lower. Pressurizer pressure drops to 2180 psig and is increasing slowly. Individual Rod Position Indication for rod M-8 indicates O. Which one of the following states the procedure that will be entered and an action that will be performed? A 3-0NOP-028, Reactor Control System Malfunction Verify shutdown margin is satisfied within one hour. B 3-0NOP-028, Reactor Control System Malfunction Reduce power to less than 90% within 30 minutes. C 3-0NOP-28.3, Dropped RCC Perform QPTR hourly until less than 50% power. D 3-0NOP-28.3, Dropped RCC Reduce Power Range Hi Flux Trip setpoint to 75% within one hour.

Turkey Point ILC 25 Question 83 Initial conditions: Unit 4 at 3% power Channel Select Pressurizer Level Controller is in Position 1 (Ch. 1 & 2) Subsequently: At 0600 letdown automatically isolates All Pressurizer heaters trip Pressurizer level begins to increase Annunciator G 111, CHARGING PUMP LO SPEED, actuates At 1000, the transmitter is still failed, but all other required 4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channel, actions have been completed. Complete the following statement. Tech Spec 3.3.1 is provided as a reference.

'.-:(1'-") __ has failed low and power increase to Mode 1 __

->.:(2=.<) __ allowed. (1) (2) A LT-4-459 is not B LT-4-459 IS C LT-4-460 is not D LT-4-460 IS Turkey Point ILC 25 Question 83 Initial conditions: Unit 4 at 3 % power Channel Select Pressurizer Level Controller is in Position 1 eCho 1 & 2) Subsequently: At 0600 letdown automatically isolates All Pressurizer heaters trip Pressurizer level begins to increase Annunciator GIll, CHARGING PUMP LO SPEED, actuates At 1000, the transmitter is still failed, but all other required 4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channel, actions have been completed. Complete the following statement. Tech Spec 3.3.1 is provided as a reference. --'-'OO.,L) __ has failed low and power increase to Mode 1 __ ->(..=2,-,-) __ allowed.

0)

(2) A LT-4-459 is not B LT-4-459 IS C LT-4-460 is not D LT-4-460 IS

Turkey Point ILC 25 Question 84 Initial conditions: Refueling is in progress on Unit 4. The ECFs are available. Containment Purge is in progress. Subsequently: The Refueling SRO reports a dropped spent fuel assembly. Gas bubbles are seen rising in the same area. R-4-11, Containment Air Particulate Process Monitor, and R-4-12, Containment Air Gaseous Process Monitor, are increasing. R-4-11 and R-4-12 are NOT in alarm. Which of the following procedures and actions should be entered and performed first? A 4-0NOP-033.3, Accidents Involving New or Spent Fuel, and start Containment Purge to filter and monitor the release. B 4-0NOP-033.3, Accidents Involving New or Spent Fuel, and start the ECFs to reduce iodine levels. C 4-0NOP-067, Radioactive Effluent Release, and start Containment Purge to filter and monitor the release. D 4-0NOP-067, Radioactive Effluent Release, and start the ECFs to reduce iodine levels. Turkey Point ILC 25 Question 84 Initial conditions: Refueling is in progress on Unit 4. The ECFs are available. Containment Purge is in progress. Subsequently: The Refueling SRO reports a dropped spent fuel assembly. Gas bubbles are seen rising in the same area. R-4-11, Containment Air Particulate Process Monitor, and R-4-12, Containment Air Gaseous Process Monitor, are increasing. R-4-11 and R-4-12 are NOT in alarm. Which of the following procedures and actions should be entered and performed first? A 4-0NOP-033.3, Accidents Involving New or Spent Fuel, and start Containment Purge to filter and monitor the release. B 4-0NOP-033.3, Accidents Involving New or Spent Fuel, and start the ECFs to reduce iodine levels. C 4-0NOP-067, Radioactive Effluent Release, and start Containment Purge to filter and monitor the release. D 4-0NOP-067, Radioactive Effluent Release, and start the ECFs to reduce iodine levels.

Turkey Point ILC 25 Question 85 The crews are performing O-ONOP-I05, Control Room Evacuation. A plant cooldown and depressurization is being performed from the Alternate Shutdown Panel. RCPs are stopped. CRDM Fans are not available. Pressurizer level starts increasing rapidly. What procedure and action(s) will address the rapidly increasing Pressurizer level? A Go to 3-EOP-ES-0.2, Natural Circulation Cooldown, and open the head vents B Go to 3-EOP-ES-O.2, Natural Circulation Cooldown, and increase charging and energize heaters C Remain in O-ONOP-I05 and open the head vents D Remain in O-ONOP-I05 and increase charging and energize heaters Turkey Point ILC 25 Question 85 The crews are performing O-ONOP-I OS, Control Room Evacuation. A plant cooldown and depressurization is being performed from the Alternate Shutdown Panel. RCPs are stopped. CRDM Fans are not available. Pressurizer level starts increasing rapidly. What procedure and action(s) will address the rapidly increasing Pressurizer level? A Go to 3-EOP-ES-0.2, Natural Circulation Cooldown, and open the head vents B Go to 3-EOP-ES-0.2, Natural Circulation Cooldown, and increase charging and energize heaters C Remain in O-ONOP-l 05 and open the head vents D Remain in 0-ONOP-I05 and increase charging and energize heaters

Turkey Point ILC 25 Question 86 Unit 3 is in Mode 5 with the following conditions: The RCS is at 110°F and 350 psig. All S/Gs narrow range levels are off-scale low. The secondary side manways have been removed. RHR is in service. All RCPs have been stopped. Subsequently MOV 750, Loop 3C RHR Pump Suction Stop Valve, closed and cannot be opened. RCS temperature is slowly increasing. Which of the following is the required mitigating strategy to establish core cooling? Note 3-0NOP-041.8, Shutdown LOCA [Mode 5 or 6] Enter 3-0NOP-050, Loss ofRHR, and... A establish natural circulation cooling B start at least one RCP, and establish forced circulation C go to 3-0NOP-041.8 to establish feed and bleed D go to 3-0NOP-041.8 to establish cold leg injection Turkey Point ILC 25 Question 86 Unit 3 is in Mode 5 with the following conditions: The RCS is at 110 0 P and 350 psig. All S/Gs narrow range levels are off-scale low. The secondary side manways have been removed. RHR is in service. All RCPs have been stopped. Subsequently MOV-3-750, Loop 3C RHRPump Suction Stop Valve, closed and cannot be opened. RCS temperature is slowly increasing. Which of the following is the required mitigating strategy to establish core cooling? Note 3-0NOP-041.8, Shutdown LOCA [Mode 5 or 6] Enter 3-0NOP-050, Loss ofRHR, and... A establish natural circulation cooling B start at least one RCP, and establish forced circulation C go to 3-0NOP-041.8 to establish feed and bleed D go to 3-0NOP-041.8 to establish cold leg injection

Turkey Point ILC 25 Question 87 Unit 3 is in Mode 1 at 100% power. There is a leak on the 3A CCW Header. The crew has split the CCW headers in accordance with 3-0NOP-030, Component Cooling Water Malfunction. In accordance with Tech Specs, what CCW Pumps are currently OPERABLE and what action(s) is/are required, if any? A The 3B and 3C CCW Pumps are OPERABLE Restore two pumps from independent power supplies within 72 hours B The 3B and 3C CCW Pumps are OPERABLE Restore 3A CCW Pump to OPERABLE within 14 days C The 3A, 3B, and 3C CCW Pumps are OPERABLE No Tech Spec actions apply D The 3A, 3B, and 3C CCW Pumps are OPERABLE Restore the 3A CCW Header to OPERABLE within 14 days. Turkey Point ILC 25 Question 87 Unit 3 is in Mode 1 at 100% power. There is a leak on the 3A CCW Header. The crew has split the CCW headers in accordance with 3-0NOP-030, Component Cooling Water Malfunction. In accordance with Tech Specs, what CCW Pumps are currently OPERABLE and what action(s) is/are required, if any? A The 3B and 3C CCW Pumps are OPERABLE Restore two pumps from independent power supplies within 72 hours B The 3B and 3C CCW Pumps are OPERABLE Restore 3A CCW Pump to OPERABLE within 14 days C The 3A, 3B, and 3C CCW Pumps are OPERABLE No Tech Spec actions apply D The 3A, 3B, and 3C CCW Pumps are OPERABLE Restore the 3A CCW Header to OPERABLE within 14 days.

Turkey Point ILC 25 Question 88 Unit 3 is at 100% power. A transient causes all 3A S/G narrow range levels to go to 8% and remain there. The reactor remains at 100% power. Complete the following statement. AMSAC will trip the reactor by opening the Rod Drive Motor Generator -->,..:(1:..,L) __

After AMSAC successfully trips the reactor, the event is alan (2)

(1) (2) A. Output Breaker Alert B. Output Breaker Site Area Emergency C. Input Breaker Alert D. Input Breaker Site Area Emergency Turkey Point ILC 25 Question 88 Unit 3 is at 100% power. A transient causes all 3A S/G narrow range levels to go to 8% and remain there. The reactor remains at 100% power. Complete the following statement. AMSAC will trip the reactor by opening the Rod Drive Motor Generator --,-,O'-.L) __. After AMSAC successfully trips the reactor, the event is alan (2) (1) (2) A. Output Breaker Alert B. Output Breaker Site Area Emergency C. Input Breaker Alert D. Input Breaker Site Area Emergency

Turkey Point ILC 25 Question 89 Initial conditions: Unit 3 is in Mode 1 The Hogging Jet is in service Subsequently: Unit 3 experiences a Safety Injection. The following is the status when the Unit Supervisor reads the diagnostic steps in 3-EOP-E-O, Reactor Trip or Safety Injection: ~ AFW has been isolated to the 3A S/G. ~ 3A S/G narrow range level is 8% and increasing. ~ 3B and 3C S/G narrow range levels are off-scale low. ~ R-15 and SJAE SPING both read pre-event values. What is the status ofR-15 and the SJAE SPING and how should the Unit Supervisor respond to the above event? A Only R-15 is OOS. Transition to 3-EOP-E-3, Steam Generator Tube Rupture. Do not wait for RP and Chemistry reports. B Only R-15 is OOS. Continue in E-O and dispatch RP and Chemistry. C R-15 and SJAE SPING are OOS. Transition to 3-EOP-E-3, Steam Generator Tube Rupture. Do not wait for RP and Chemistry reports. D R-15 and SJAE SPING are OOS. Continue in E-O and dispatch RP and Chemistry. Turkey Point ILC 25 Question 89 Initial conditions: Unit 3 is in Mode 1 The Hogging Jet is in service Subsequently: Unit 3 experiences a Safety Injection. The following is the status when the Unit Supervisor reads the diagnostic steps in 3-EOP-E-O, Reactor Trip or Safety Injection: ~ AFW has been isolated to the 3A S/G. ~ 3A S/G narrow range level is 8% and increasing. ~ 3B and 3C S/G narrow range levels are off-scale low. ~ R-15 and SJAE SPING both read pre-event values. What is the status ofR-15 and the SJAE SPING and how should the Unit Supervisor respond to the above event? A Only R-15 is OOS. Transition to 3-EOP-E-3, Steam Generator Tube Rupture. Do not wait for RP and Chemistry reports. B Only R-15 is OOS. Continue in E-O and dispatch RP and Chemistry. C R-15 and SJAE SPING are OOS. Transition to 3-EOP-E-3, Steam Generator Tube Rupture. Do not wait for RP and Chemistry reports. D R-15 and SJAE SPING are OOS. Continue in E-O and dispatch RP and Chemistry.

Turkey Point ILC 25 Question 90 Initial conditions: The crew is performing 3-GOP-301, Hot Standby to Power Operation. The BOP is preparing to manually sync the generator to the grid. Immediately after the BOP manually closed the East Bus Breaker, the following alarms and indications were received: >> F 8/1 INADVERTENT ENERGIZATION GENERATOR TRIP >> B 1/1 RX COOLANT LOOP A LO FLOW >> Breaker 3AA05, 4kV Bus 3A Feed from Unit 3 Startup XFMR, opened What is the reason for these alarms and the required actions? The BOP closed the generator output breaker... A out of phase with the grid. Trip the reactor and be in Mode 3 in 6 hours B out of phase with the grid. Trip the reactor and be in Mode 3 in 12 hours C in a reverse power condition. Trip the reactor and be in Mode 3 in 6 hours D in a reverse power condition. Trip the reactor and be in Mode 3 in 12 hours Turkey Point ILC 25 Question 90 Initial conditions: The crew is performing 3-GOP-301, Hot Standby to Power Operation. The BOP is preparing to manually sync the generator to the grid. Immediately after the BOP manually closed the East Bus Breaker, the following alarms and indications were received: >> F 8/1 INADVERTENT ENERGIZATION GENERATOR TRIP >> B 1/1 RX COOLANT LOOP A LO FLOW >> Breaker 3AA05, 4kV Bus 3A Feed from Unit 3 Startup XFMR, opened What is the reason for these alarms and the required actions? The BOP closed the generator output breaker... A out of phase with the grid. Trip the reactor and be in Mode 3 in 6 hours B out of phase with the grid. Trip the reactor and be in Mode 3 in 12 hours C in a reverse power condition. Trip the reactor and be in Mode 3 in 6 hours D in a reverse power condition. Trip the reactor and be in Mode 3 in 12 hours

Turkey Point ILC 25 Question 91 PRMS-R-18 (R-18), Liquid Radwaste Effluent Process Monitor, is out of service. There are no Circulating Water Pumps (CWPs) running. In accordance with O-OP-061.11, Waste Disposal System Controlled Radiological Release, which of the following is required for the Shift Manager to approve the release of a Monitor Tank? A A Monitor Tank cannot be released with R-18 out of service. A Unit 3 OR Unit 4 CWP must be running. B Compensatory actions can be taken for R-18 out of service. A Unit 3 OR Unit 4 CWP must be running. C A Monitor Tank cannot be released with R-18 out of service. A Unit 3 AND Unit 4 CWP must be running. D Compensatory actions can be taken for R-18 out of service. A Unit 3 AND Unit 4 CWP must be running. Turkey Point ILC 25 Question 91 PRMS-R-18 (R-18), Liquid Radwaste Effluent Process Monitor, is out of service. There are no Circulating Water Pumps (CWPs) running. In accordance with O-OP-061.11, Waste Disposal System Controlled Radiological Release, which of the following is required for the Shift Manager to approve the release of a Monitor Tank? A A Monitor Tank cannot be released with R-18 out of service. A Unit 3 OR Unit 4 CWP must be running. B Compensatory actions can be taken for R -18 out of service. A Unit 3 OR Unit 4 CWP must be running. C A Monitor Tank cannot be released with R -18 out of service. A Unit 3 AND Unit 4 CWP must be running. D Compensatory actions can be taken for R -18 out of service. A Unit 3 AND Unit 4 CWP must be running.

Turkey Point ILC 25 Question 92 The B Waste Gas Decay Tank is being released. - PRMS R-14, Plant Vent Gaseous Effluent Monitor, fails high. RCV-014, GDT to Plant Vent Control Valve, does not close. In accordance with 3-0NOP-067, Radioactive Effluent Release, the crew should....\\.(-=.,1).1....-..._ to stop the release and according to the ODCM (2) must be done to resume the release. A Stop the Auxiliary Building Exhaust Fans Plant Vent SPING verified operable. B Stop the Auxiliary Building Exhaust Fans Two independent samples of the GDT analyzed, an independent verification of release rate calculation, and IV discharge valve lineup. C Locally close RCV-014 isolation, 4638B Plant Vent SPING verified operable. D Locally close RCV-014 isolation, 4638B Two independent samples of the GDT analyzed, an independent verification of release rate calculation, and IV discharge valve lineup. Turkey Point ILC 25 Question 92 The B Waste Gas Decay Tank is being released. - PRMS R-14, Plant Vent Gaseous Effluent Monitor, fails high. RCV -014, GDT to Plant Vent Control Valve, does not close. In accordance with 3-0NOP-067, Radioactive Effluent Release, the crew should...l.(~1).l....-.-_ to stop the release and according to the ODCM (2) must be done to resume the release. A Stop the Auxiliary Building Exhaust Fans Plant Vent SPING verified operable. B Stop the Auxiliary Building Exhaust Fans Two independent samples of the GDT analyzed, an independent verification of release rate calculation, and IV discharge valve lineup. C Locally close RCV-014 isolation, 4638B Plant Vent SPING verified operable. D Locally close RCV-014 isolation, 4638B Two independent samples of the GDT analyzed, an independent verification of release rate calculation, and IV discharge valve lineup.

Turkey Point ILC 25 Question 93 Both units have performed a Control Room evacuation in accordance with O-ONOP-l05, Control Room Evacuation. No Instrument Air Compressor is available. Instrument Air pressure is 90 psig and lowering. What are the 50.54(x) declaration requirements and basis to align Service Air to Instrument Air under these conditions? A Align Service Air to the Instrument Air System without a 50.54(x) declaration. Instrument Air is needed for a normal shutdown. B Align Service Air to the Instrument Air System without a 50.54(x) declaration. Instrument Air is needed for an Appendix R shutdown. C Align Service Air to the Instrument Air System after a 50.54(x) declaration. Instrument Air is needed for a normal shutdown. D Align Service Air to the Instrument Air System after a 50.54(x) declaration. Instrument Air is needed for an Appendix R shutdown. Turkey Point ILC 2S Question 93 Both units have performed a Control Room evacuation in accordance with O-ONOP-lOS, Control Room Evacuation. No Instrument Air Compressor is available. Instrument Air pressure is 90 psig and lowering. What are the SO.S4(x) declaration requirements and basis to align Service Air to Instrument Air under these conditions? A Align Service Air to the Instrument Air System without a SO.S4(x) declaration. Instrument Air is needed for a normal shutdown. B Align Service Air to the Instrument Air System without a SO.S4(x) declaration. Instrument Air is needed for an Appendix R shutdown. C Align Service Air to the Instrument Air System after a SO.S4(x) declaration. Instrument Air is needed for a normal shutdown. D Align Service Air to the Instrument Air System after a SO.S4(x) declaration. Instrument Air is needed for an Appendix R shutdown.

Turkey Point ILC 25 Question 94 3-EOP-E-3, Stearn Generator Tube Rupture, is being performed following a safety injection with R-15 pegged high. Chemistry and HP both report no abnormal readings associated with the S/Gs. All 3 S/Gs indicate normal and stable level indications. All 3 S/G pressures are stable. Auxiliary Building radiation levels are normal. Containment process monitors R-ll/R-12 were increasing until isolated. In accordance with O-ADM-211, Emergency and Off-Normal Procedure Usage, which one of the following is correct? A Go to 3-EOP-ES-O.O, Rediagnosis, then go to 3-EOP-E-1, Loss of Reactor or Secondary Coolant. B Go to 3-EOP-ES-O.O, Rediagnosis, then go to 3-EOP-ECA-1.2, LOCA Outside Containment. C Go to 3-EOP-E-2, Faulted Stearn Generator Isolation, then go to 3-EOP-E-l, Loss of Reactor or Secondary Coolant. D Continue in 3-EOP-E-3, Stearn Generator Tube Rupture, then go 3-EOP-ECA-3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired. Turkey Point ILC 25 Question 94 3-EOP-E-3, Steam Generator Tube Rupture, is being performed following a safety injection with R-15 pegged high. Chemistry and HP both report no abnormal readings associated with the S/Gs. All 3 S/Gs indicate normal and stable level indications. All 3 S/G pressures are stable. Auxiliary Building radiation levels are normal. Containment process monitors R-11/R-12 were increasing until isolated. In accordance with O-ADM-211, Emergency and Off-Normal Procedure Usage, which one ofthe following is correct? A Go to 3-EOP-ES-O.O, Rediagnosis, then go to 3-EOP-E-1, Loss of Reactor or Secondary Coolant. B Go to 3-EOP-ES-O.O, Rediagnosis, then go to 3-EOP-ECA-1.2, LOCA Outside Containment. C Go to 3-EOP-E-2, Faulted Steam Generator Isolation, then go to 3-EOP-E-1, Loss of Reactor or Secondary Coolant. D Continue in 3-EOP-E-3, Steam Generator Tube Rupture, then go 3-EOP-ECA-3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired.

Turkey Point ILC 25 Question 95 Unit 4 is at 100% power. Reactor Engineering reports that rod L-5 is known to be untrippable. Which one of the following identifies the required Tech Spec actions and the earliest required notification to the NRC for the above condition? Reference provided A Reduce thermal power to less than 90% within 1 hour or be in Hot Standby within 6 hours. Notify the NRC within 1 hour. B Determine shutdown margin satisfied within 1 hour and be in Hot Standby within 6 hours. Notify the NRC within 1 hour. C Reduce thermal power to less than 90% within 1 hour or be in Hot Standby within 6 hours. Notify NRC within 4 hours. D Determine shutdown margin satisfied within 1 hour and be in Hot Standby within 6 hours. Notify NRC within 4 hours. Turkey Point ILC 25 Question 95 Unit 4 is at 100% power. Reactor Engineering reports that rod L-5 is known to be untrippable. Which one of the following identifies the required Tech Spec actions and the earliest required notification to the NRC for the above condition? Reference provided A Reduce thennal power to less than 90% within 1 hour or be in Hot Standby within 6 hours. Notify the NRC within 1 hour. B Detennine shutdown margin satisfied within 1 hour and be in Hot Standby within 6 hours. Notify the NRC within 1 hour. C Reduce thennal power to less than 90% within 1 hour or be in Hot Standby within 6 hours. Notify NRC within 4 hours. D Detennine shutdown margin satisfied within 1 hour and be in Hot Standby within 6 hours. Notify NRC within 4 hours.

Turkey Point ILC 25 Question 96 A temporary system alteration (TSA) has been approved by the PNSC. In accordance with O-ADM-503, Temporary System Alterations, who will give final approval for the TSA after approval by the PNSC and who will approve the implementation of the TSA? TSA approval TSA implementation approval A Site Engineering Manager Shift Manager B Plant General Manager Project Engineer C Plant General Manager Shift Manager D Site Engineering Manager Project Engineer Turkey Point ILC 25 Question 96 A temporary system alteration (TSA) has been approved by the PNSC. In accordance with O-ADM-503, Temporary System Alterations, who will give final approval for the TSA after approval by the PNSC and who will approve the implementation of the TSA? TSA approval TSA implementation approval A Site Engineering Manager Shift Manager B Plant General Manager Project Engineer C Plant General Manager Shift Manager D Site Engineering Manager Project Engineer

Turkey Point ILC 25 Question 97 Initial conditions: Unit 3 is at 100% power. The SJAE SPING is out of service. Subsequently, the Flow Rate Measuring Device for PRMS R-3-15, Condenser Air Ejector Gaseous Monitor, is declared OOS. In accordance with the ODCM, what action, if any, must be performed because the Flow Rate Measuring Device is out of service? Reference provided A No actions required B Install auxiliary equipment and verify sample flow rate every 4 hours C Estimate the flow rate at least every 4 hours D Grab samples taken every 12 hours and analyzed within 24 hours Turkey Point ILC 25 Question 97 Initial conditions: Unit 3 is at 100% power. The SJAE SPING is out of service. Subsequently, the Flow Rate Measuring Device for PRMS R-3-l5, Condenser Air Ejector Gaseous Monitor, is declared OOS. In accordance with the ODCM, what action, if any, must be performed because the Flow Rate Measuring Device is out of service? Reference provided A No actions required B Install auxiliary equipment and verify sample flow rate every 4 hours C Estimate the flow rate at least every 4 hours D Grab samples taken every 12 hours and analyzed within 24 hours

Turkey Point ILC 25 Question 98 Core alterations in Unit 3 Containment were in progress. Area Radiation Monitor (ARMS) R-2, 58' Elevation, has a broken dose rate indicator on the local monitor. In accordance with 3-0P-038.1, Preparation for Refueling Activities, which one of the following will allow the Refueling SRO to resume core alterations? A Control Room functions for ARMS R-2 verified operable every 15 minutes B Local indication for ARMS R-2 replaced with portable monitor with alarm C Dedicated operator to constantly monitor Control Room ARMS R-2 D RP survey of the 58' elevation every 15 minutes Turkey Point ILC 25 Question 98 Core alterations in Unit 3 Containment were in progress. Area Radiation Monitor (ARMS) R-2, 58' Elevation, has a broken dose rate indicator on the local monitor. In accordance with 3-0P-038.1, Preparation for Refueling Activities, which one of the following will allow the Refueling SRO to resume core alterations? A Control Room functions for ARMS R-2 verified operable every 15 minutes B Local indication for ARMS R-2 replaced with portable monitor with alarm C Dedicated operator to constantly monitor Control Room ARMS R-2 D RP survey of the 58' elevation every 15 minutes

Turkey Point ILC 25 Question 99 Unit 3 tripped 20 minutes ago from 100% power with the following conditions: Containment temperature 190°F Containment pressure 22 psig Containment Recirculation Sump level 450 inches Tcolds 340°F All Steam Generator narrow range levels AFW fiowrates 30% 120 gpm to 3A S/G 120 gpm to 3B S/G 120 gpm to 3C S/G What Functional Restoration Procedure should be implemented first? A 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink B 3-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Conditions C 3-EOP-FR-Z.1, Response to High Containment Pressure D 3-EOP-FR-Z.2, Response to Containment Flooding Turkey Point ILC 25 Question 99 Unit 3 tripped 20 minutes ago from 100% power with the following conditions: Containment temperature 190°F Containment pressure 22 psig Containment Recirculation Sump level 450 inches Thcl~ 3~~ All Steam Generator narrow range levels AFW flowrates 30% 120 gpm to 3A S/G 120 gpm to 3B S/G 120 gpm to 3C S/G What Functional Restoration Procedure should be implemented first? A 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink B 3-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Conditions C 3-EOP-FR-Z.1, Response to High Containment Pressure D 3-EOP-FR-Z.2, Response to Containment Flooding

Turkey Point ILC 25 Question 100 Unit 3 is at 100% power. A fire alarm is received for the Unit 3 Charging Pmnp Room. The fire is confirmed by the SNPO. The Fire Brigade has been dispatched. According to 0-ONOP-016.10, Pre-Fire Plan Guidelines and Safe Shutdown Manual Actions, which one of the following conditions would require the Unit Supervisor to initiate safe shutdown manual actions? A The fire has spread to the Boric Acid Batch Tank Room B Occurrence of multiple spurious equipment malfunctions or failures C The Fire Brigade Leader requests off-site support D The Fire Brigade takes 12 minutes to get to the fire Turkey Point ILC 25 Question 100 Unit 3 is at 100% power. A fire alarm is received for the Unit 3 Charging Pump Room. The fire is confirmed by the SNPO. The Fire Brigade has been dispatched. According to 0-ONOP-016.10, Pre-Fire Plan Guidelines and Safe Shutdown Manual Actions, which one of the following conditions would require the Unit Supervisor to initiate safe shutdown manual actions? A The fire has spread to the Boric Acid Batch Tank Room B Occurrence of multiple spurious equipment malfunctions or failures C The Fire Brigade Leader requests off-site support D The Fire Brigade takes 12 minutes to get to the fire

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I I I I I I I I I J I I I 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I Page: 39 Approval Date: 8/29/07 o I 5 I 10 I 15 I 20 25 30 I 35 I 40 45 I 50 I 55 I 60 Time Since Shutdown 150 MWD/MTU B/U - B/U B/U = 7,000 MWD/MTU 16,500 MWD/MTU

Procedure No.: Procedure

Title:

Page: 10 Approval Date: O-ADM-115 Notification of Plant Events 5/15/08 ENCLOSURE 1 (Page 1 of7) NRC NOTIFICATION TABLE Plant Condition or Event Notification Notes Time Limit Deviation from Tech Specs allowed by 10CFR 50.54(x) One Hour ..... Perform actions immediately necessary to protect public health and safety. /./... --'\\ 1\\ 10CFR 50.72(b)(1) ! Initiation of any nuclear plant shutdown required by Tech. (Four HoUl~ "Initiation of any Nuclear Plant Shutdown" is the performance of any Specs. ..""'._.... -*..,,... / action to start reducing reactor power to achieve an operational condition or mode that requires the reactor to be subcritical as a result of a Tech Spec requirement. This includes any means of power reduction, such as control rod insertion, boration or turbine load reduction [NUREG-I 022]. Examples are exceeding an LCO action statement, Tech Spec 3.0.3, Safety Limit violation [10CFR 50.36]. 10CFR 50.72(b)(2)(i) An event that results or should have resulted in Four Hours Actuation from a pre-planned sequence during testing or reactor operation Emergency Core Cooling System discharge into the RCS is not reportable. as a result of a valid signal. 10CFR 50.72(b)(2)(iv)(A) An event that results in actuation of the Reactor Four Hours Manual or automatic RPS actuation not part of a pre-planned sequence is Protection System (RPS) when the reactor is critical. reportable. Actuation from a pre-planned sequence during testing or reactor operation is not reportable. Turbine runbacks are not part ofRPS and therefore not reportable. 10CFR 50.72(b)(2)(iv)(B) One startup transformer and one of the required Four Hours emergency diesel generators inoperable. Tech Spec 3.8.1.1. Both startup transformers inoperable. Four Hours Tech Spec 3.8.1.1. Both standby feedwaterpumps inoperable for 24 hours. Four Hours Tech Spec 3.7.1.6. W2002/AWT/cls/c1s/c1s Procedu're No.: Procedure

Title:

Page: 10 Approval Date: O-ADM-115 Notification of Plant Events 5/15/08 ENCLOSURE 1 (Page 1 of7) NRC NOTIFICATION TABLE Plant Condition or Event Notification Notes Time Limit Deviation from Tech Specs allowed by 10CFR 50.54(x) One Hour Perform actions immediately necessary to protect public health and safety. -~\\ 10CFR 50.72(b)(1) Initiation of any nuclear plant shutdown required by Tech, Four HourS "Initiation of any Nuclear Plant Shutdown" is the performance of any Specs. action to start reducing reactor power to achieve an operational condition or mode that requires the reactor to be subcritical as a result of a Tech Spec requirement. This includes any means of power reduction, such as control rod insertion, boration or turbine load reduction [NUREG-I 022]. Examples are exceeding an LCO action statement, Tech Spec 3.0.3, Safety Limit violation [IOCFR 50.36]. 10CFR 50.72(b)(2)(i) An event that results or should have resulted in Four Hours Actuation from a pre-planned sequence during testing or reactor operation Emergency Core Cooling System discharge into the RCS is not reportable. as a result of a valid signal. 1 OCFR 50.72(b )(2)(iv)(A) An event that results in actuation of the Reactor Four Hours Manual or automatic RPS actuation not part of a pre-planned sequence is Protection System (RPS) when the reactor is critical. reportable. Actuation from a pre-planned sequence during testing or reactor operation is not reportable. Turbine runbacks are not part ofRPS and therefore not reportable. I OCFR 50.72(b )(2)(iv)(B) One startup transformer and one of the required Four Hours emergency diesel generators inoperable. Tech Spec 3.S.1.1. Both startup transformers inoperable. Four Hours Tech Spec 3.S.1.l. Both standby feedwater pumps inoperable for 24 hours. Four Hours Tech Spec 3.7.1.6. W2002/Awr /cls/cls/cls

Procedure No.: Procedure

Title:

0-ADM-115 Plant Condition or Event A major loss of emergency assessment capability W2002/AWT/cls/cls/cls Notification Time Limit Eight Hours Notification of Plant Events ENCLOSURE 1 (Page 2 of7) NRC NOTIFICATION TABLE Examples are: Notes Page: 11 Approval Date: 5/15/08 The loss of significant portion of Control Room indication, including indicators, annunciators, and monitors used for accident assessment, of the complete loss of all plant vent stack radiation monitors. The complete loss of ERDADS/DCS data concurrent with the loss of other major accident assessment indication (indicators, annunciators, monitors, etc.). The complete loss ofERDADS/DCS for greater than one hour. This includes the loss of the capability to transmit data to the ERDS communications link, but is separate from the ERDS communications link requirement. Additional guidance:

1.

A significant loss of Control Room indication, including annunciators and monitors used to obtain Emergency Plan data, would be a condition where the capability to perform a complete safety assessment, such as for an Emergency Plan evaluation, would not be possible.

2.

The loss of all plant vent stack radiation monitors would be considered a significant loss of assessment capability and would be reportable.

3.

The complete loss ofERDADS/DCS data concurrent with the loss of other major accident assessment indication (indicators, annunciators, monitors, etc.) would be considered a significant loss of assessment capability and would be reportable.

4.

If an emergency assessment system or component is governed by a Technical Specifications, ODCM, or UFSAR requirement, and operation is permitted within the LCO Action statement, then there is NOT a significant loss of assessment capability (e.g. - accident monitoring equipment, radiation monitors, meteorological equipment, etc.). If the governing document requires NRC notification or plant shutdown due to unavailable assessment instrumentation, then a condition would be considered a significant loss of assessment capability and would be reportable.

5.

The loss of some data points, where alternate means are available to obtain the same required accident assessment data, would NOT constitute a significant loss of assessment capability.

6.

The loss of all meteorological tower data points, where the National Weather Service can provide the required information, would NOT constitute a significant loss of assessment capability. IOCFR 50.72(b)(3)(xiii) Procedure No.: Procedure

Title:

O-ADM-115 Plant Condition or Event A major loss of emergency assessment capability W2002/Awr/cls/cls/cls Notification Time Limit Eight Hours Notification of Plant Events ENCLOSURE 1 (Page 2 of7) NRC NOTIFICATION TABLE Examples are: Page: 11 Approval Date: 5/15/08 Notes The loss of significant portion of Control Room indication, including indicators, annunciators, and monitors used for accident assessment, of the complete loss of all plant vent stack radiation monitors. The complete loss of ERDADS/DCS data concurrent with the loss of other major accident assessment indication (indicators, annunciators, monitors, etc.). The complete loss of ERDADS/DCS for greater than one hour. This includes the loss of the capability to transmit data to the ERDS communications link, but is separate from the ERDS communications link requirement. Additional guidance:

1.

A significant loss of Control Room indication, including annunciators and monitors used to obtain Emergency Plan data, would be a condition where the capability to perform a complete safety assessment, such as for an Emergency Plan evaluation, would not be possible.

2.

The loss of all plant vent stack radiation monitors would be considered a significant loss of assessment capability and would be reportable.

3.

The complete loss ofERDADSIDCS data concurrent with the loss of other major accident assessment indication (indicators, annunciators, monitors, etc.) would be considered a significant loss of assessment capability and would be reportable.

4.

If an emergency assessment system or component is governed by a Technical Specifications, ODCM, or UFSAR requirement, and operation is permitted within the LCO Action statement, then there is NOT a significant loss of assessment capability (e.g. - accident monitoring equipment, radiation monitors, meteorological equipment, etc.). If the governing document requires NRC notification or plant shutdown due to unavailable assessment instrumentation, then a condition would be considered a significant loss of assessment capability and would be reportable.

5.

The loss of some data points, where alternate means are available to obtain the same required accident assessment data, would NOT constitute a significant loss of assessment capability.

6.

The loss of all meteorological tower data points, where the National Weather Service can provide the required information, would NOT constitute a significant loss of assessment capability. 10CFR 50.72(b)(3)(xiii)

Procedure No.: Procedure

Title:

0-ADM-115 Plant Condition or Event A major loss of off-site response capability A major loss of off-site communications capability Steam generator tube inspection results in Category C-3. Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems necessary to: Shut down the reactor and maintain it in a safe shutdown condition Remove residual heat Control the release of radioactive material Mitigate the consequences of an accident W2002/AWT/cls/cls/cis Page: 12 Approval Date: Notification of Plant Events 11/4/08 ENCLOSURE 1 (Page 3 of7) NRC NOTIFICATION TABLE Notification Time Limit Notes Eight Hours I Examples are: Eight Hours Eight Hours Loss of primary and back-up off-site emergency response equipment. Loss of major roadway access to plant site. 10CFR SO.72(b )(3)(xiii) Examples are: Loss of ENS telephone. Loss of primary and all backup State communications channels. Significant degradation of the Alert and Notification System (siren availability less than 90 percent for 12 consecutive months, or less than 7S percent for 2 weeks). [Commitment - Steps 2.3.1 and 2.3.2] Loss of telephone line or modem for the Emergency Response Data System (ERDS), for any length of time. Loss of an FTS-200 1 communications link (ENS, ERDS, etc.). Once notified of an FTS-200 1 problem, the NRC is responsible for any corrective actions, unless the problem is within the Plant Telephone System. If the NRC notifies the licensee that an ENS line is inoperable, there is no need for a subsequent licensee notification; however, the licensee should ensure that the NRC has contacted the appropriate repair organization. 10CFR SO.72(b)(3)(xiii) Tech Spec 4.4.S.S.c Eight Hours I Systems with operable redundant trains do not meet this criteria. 1 OCFR SO.72(b )(3)(v)(A-B-C-D) Procedure No.: Procedure

Title:

0-ADM-115 Plant Condition or Event A major loss of off-site response capability A major loss of off-site communications capability Page: 12 Approval Date: Notification of Plant Events 11/4/08 ENCLOSURE 1 (Page 3 of7) NRC NOTIFICATION TABLE Notification Time Limit Notes Eight Hours Examples are: Loss of primary and back-up off-site emergency response equipment. Loss of major roadway access to plant site. 10CFR 50.72(b)(3)(xiii) Eight Hours Examples are: Loss of ENS telephone. Loss of primary and all backup State communications channels. Significant degradation of the Alert and Notification System (siren availability less than 90 percent for 12 consecutive months, or less than 75 percent for 2 weeks). [Commitment - Steps 2.3.1 and 2.3.2] Loss of telephone line or modem for the Emergency Response Data System (ERDS), for any length of time. Loss of an FTS-2001 communications link (ENS, ERDS, etc.). Once notified of an FTS-200 1 problem, the NRC is responsible for any corrective actions, unless the problem is within the Plant Telephone System. If the NRC notifies the licensee that an ENS line is inoperable, there is no need for a subsequent licensee notification; however, the licensee should ensure that the NRC has contacted the appropriate repair organization. 10CFR 50.72(b)(3)(xiii) Steam generator tube inspection results in Category Eight Hours C-3. Tech Spec 4.4.5.5.c Any event or condition that at the time of discovery Eight Hours Systems with operable redundant trains do not meet this criteria. could have prevented the fulfillment of the safety function of structures or systems necessary to: Shut down the reactor and maintain it in a safe shutdown condition Remove residual heat Control the release ofradioactive material Mitigate the consequences of an accident 10CFR 50.72(b)(3)(v)(A-B-C-D) W2002/AWT/cls/cls/cls

Procedure No.: Procedure

Title:

O-ADM-115 Plant Condition or Event Notification of Plant Events ENCLOSURE 1 (Page 4 of7) NRC NOTIFICATION TABLE Notification Time Limit Page: 13 Approval Date: 5/15/08 Notes Any event or condition that results in valid actuation of I Eight Hours Valid ESF actuations are those that result from valid signals or from intentional manual initiation. any of the systems listed below except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation: Reactor Protection System General Containment Isolation signals affecting containment isolation valves in more than one system or multiple MSIVs ECCS including HHSI and RHR AFW Containment heat removal and depressurization systems, including containment spray and fan cooler systems (Ctmt Spray, ECCs, ECFs) EDGs An event or condition that results in: The nuclear plant, including its principal safety barriers, being seriously degraded. An unanalyzed condition that significantly degrades plant safety. Spent fuel pool water level below 56_ ft 19 in for 7 days W2002/AWf/cls/cls/cls Eight Hours 24 Hours Valid signals are those signals that are initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the safety function of the system. RPS actuations that occur when the reactor is not critical should not be referred to as reactor trips in event notifications. 10CFR 50.72(b)(3)(iv)(A) This includes events or conditions both during operation and shutdown. Examples are: Fuel cladding failures in the reactor or in the storage pool that are unique or wide spread, or caused by unexpected factors, and cause a significant release of fission products. Cracks or breaks in reactor coolant piping, reactor vessel, or major components in the primary coolant circuit that have safety relevance. Significant welding or material defects in the RCS. Serious pressure or temperature transients. Loss of containment integrity. Loss of pressurizer safety valves function during operation 10CFR 50.72(b)(31(ij)LA~~1 Reference Tech SJ2ec 3.9.11 Procedure No.: Procedure

Title:

O-ADM-115 Plant Condition or Event Notification of Plant Events ENCLOSURE 1 (Page 4 of7) NRC NOTIFICATION TABLE Notification Time Limit Page: 13 Approval Date: 5/15/08 Notes Any event or condition that results in valid actuation of Eight Hours Valid ESF actuations are those that result from valid signals or from intentional manual initiation. any of the systems listed below except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation: Reactor Protection System General Containment Isolation signals affecting containment isolation valves in more than one system or multiple MSIVs ECCS including HHSI and RHR AFW Containment heat removal and depressurization systems, including containment spray and fan cooler systems (Ctmt Spray, ECCs, ECFs) EDGs An event or condition that results in: The nuclear plant, including its principal safety barriers, being seriously degraded. An unanalyzed condition that significantly degrades plant safety. Spent fuel pool water level below 56 ft 10 in for 7 days W2002/AWT/cls/cls/cls Eight Hours 24 Hours Valid signals are those signals that are initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the safety function of the system. RPS actuations that occur when the reactor is not critical should not be referred to as reactor trips in event notifications. 10CFR 50.72(b)(3)(iv)(A) This includes events or conditions both during operation and shutdown. Examples are: Fuel cladding failures in the reactor or in the storage pool that are unique or wide spread, or caused by unexpected factors, and cause a significant release of fission products. Cracks or breaks in reactor coolant piping, reactor vessel, or major components in the primary coolant circuit that have safety relevance. Significant welding or material defects in the RCS. Serious pressure or temperature transients. Loss of containment integrity. Loss of pressurizer safety valves function during operation 10CFR 50.72(b)(3)(ii)(A&B) Reference Tech Spec 3.9.11

Procedure No.: Procedure

Title:

Page: 14 Approval Date: 0-ADM-115 Notification of Plant Events 5/15/08 ENCLOSURE 1 (Page 5 of7) NRC NOTIFICATION TABLE Radioactive Material Event Notification Notes Time Limit Any incident involving radioactive materials which may have caused or threatens to cause: Immediate An individual to receive a total effective dose equivalent of 25 rems or more, OR an eye dose equivalent of 75 rems or more, OR a shallow-dose equivalent to the skin or extremities of 250 rads or more. The release of radioactive material such that, had an individual been present for 24 hours, the individual could have received an intake 5 times the occupational limit on intake (not applicable to spaces not normally occupied). 10CFR 20.2202(a)(l&2) Receipt of any package that is found to contain: Immediate Removable radioactive surface contamination in excess of22 dpmlcm2; OR In excess of 200 milliremlhour on the accessible external surface [or 1000 milliremlhour under certain conditions specified in 10CFR 71.47(a)], OR I, In excess of200 milliremlhour at any point on the outer surface of the vehicle; OR In excess of 10 milliremlhour at any point two meters from the vehicle; OR 10CFR 71.87, 10CFR 71.47, Two milliremlhour in any normally occupied positions of the vehicle. 10CFR 20.l906(d) Any lost, stolen, or missing licensed material in an aggregate quantity equal to or greater than Immediate 1,000 times the quantity specified in Appendix C to I OCFR 20. 10CFR 20.220 1 (a)(l)(i) Any event requiring the transport of a radioactively contaminated person to an offsite medical Eight Hours facility for treatment. 10CFR 50.72(b)(3)(xii) Any incident involving radioactive materials which may have caused or threatens to cause: 24 hours An individual to receive, in a period of24 hours, a total effective dose equivalent of greater than 5 rems, OR an eye dose equivalent of greater than 15 rems, OR a shallow dose equivalent to the skin or extremities of greater than 50 rems. The release of radioactive material such that, had an individual been present for 24 hours, the individual could have received an intake greater than the occupational annual limit on intake (not applicable to spaces not normally occupied). 10CFR 20.2202(b)(1&2) Lost, stolen or missing licensed material in an aggregate quantity greater than 10 times the 30 days quantity specified in Appendix C to 10CFR 20, that is still missing. 10CFR 20.220 1 (a)(1)(ii) W2002/AWT/cls/cls/cis Procedure No.: Procedure

Title:

Page: 14 Approval Date: O-ADM-1l5 Notification of Plant Events 5/15/08 ENCLOSURE 1 (Page 5 of7) NRC NOTIFICATION TABLE Radioactive Material Event Notification Notes Time Limit Any incident involving radioactive materials which may have caused or threatens to cause: Immediate An individual to receive a total effective dose equivalent of25 rems or more, OR an eye dose equivalent of75 rems or more, OR a shallow-dose equivalent to the skin or extremities of250 rads or more. The release of radioactive material such that, had an individual been present for 24 hours, the individual could have received an intake 5 times the occupational limit on intake (not applicable to spaces not normally occupied). 10CFR 20.2202(a)(1&2) Receipt of any package that is found to contain: Immediate Removable radioactive surface contamination in excess of 22 dpmlcm 2

OR In excess of 200 milliremlhour on the accessible external surface [or 1000 milliremlhour under certain conditions specified in 10CFR 71.47(a)], OR In excess of200 milliremlhour at any point on the outer surface of the vehicle; OR In excess of 10 milliremlhour at any point two meters from the vehicle; OR 10CFR 71.87, 10CFR 71.47, Two millirem/hour in any normally occupied positions of the vehicle.

1 OCFR 20.1906( d) Any lost, stolen, or missing licensed material in an aggregate quantity equal to or greater than Immediate 1,000 times theguantity specified in Appendix C to I OCFR 20. 10CFR 20.220 1 (a)(1)(i) Any event requiring the transport of a radioactively contaminated person to an offsite medical Eight Hours facility for treatment. 10CFR 50.72(b)(3)(xii) Any incident involving radioactive materials which may have caused or threatens to cause: 24 hours An individual to receive, in a period of 24 hours, a total effective dose equivalent of greater than 5 rems, OR an eye dose equivalent of greater than 15 rems, OR a shallow dose equivalent to the skin or extremities of greater than 50 rems. The release ofradioactive material such that, had an individual been present for 24 hours, the individual could have received an intake greater than the occupational annual limit on intake inot al'plicable to spaces not normally occupied). 10 CFR 20.2202(b)( 1 &2) Lost, stolen or missing licensed material in an aggregate quantity greater than 10 times the 30 days quantity specified in Appendix C to 1 OCFR 20, that is still missing. 1 OCFR 20.220 1 (a)(1 )(ii) W2002/AWT/cls/cls/cls

Procedure No.: Procedure

Title:

Page: 15 Approval Date: O-ADM-115 Notification of Plant Events 8/14/08 ENCLOSURE 1 (Page 6 of7) NRC NOTIFICATION TABLE Security / Newsworthy / Employee Events Notification Time Limit Security related events requiring one hour reporting to the lOne hour NRCOC are contained in SDP-IOO, Safeguards Event Reporting. Any event or situation related to the health and safety of the I Four hours public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made (excludes contaminated groundwater incidents as described in ). Fitness For Duty Event I 24 hours W2002/AWTlcls/cls/cls Notes The Security Manager or designee will inform the Shift Manager of notifications made and actions taken. The Shift Manager will notifY the NRCOC of security related events requiring one hour notifications. 10CFR 73.71(a & b) Examples of newsworthy events are: Inadvertent release of radioactively contaminated materials. Any notification to a government agency. On-site fatality, or injury to three or more individuals all requiring in-patient hospitalization. OSHA regulations (29 CFR 1904.39) require reporting onsite fatalities, or the death of an employee from a work-related incident, or the in-patient hospitalization of 3 or more employees as a result of a work-related incident, within 8 hours. The OSHA phone number is listed in the Emergency Response Directory (Government Organizations Section). Assure the Duty Safety Supervisor is aware of this OSHA notification requirement. Assure the Shift Manager follows up with an NRC notification. 10CFR 50.72(b)(2)(xD_ Examples are: Sale, use, or possession of illegal drugs or alcohol within the Protected Area. Any acts by any person licensed under 10CFR Part 55 to operate a power reactor, or by any supervisory person assigned to perform duties within the scope of this part (10CFR Part 26), such as: o Sale, use, or possession of a controlled substance o Positive tests on such persons o Use of alcohol within the Protected Area o Unfit for duty due to the consumption of alcohol 10CFR26.73,0-ADM-OlS Procedure No.: Procedure

Title:

Page: 15 Approval Date: O-ADM-l15 Notification of Plan t Even ts 8/14/08 ENCLOSURE 1 (Page 6 of7) NRC NOTIFICATION TABLE Security / Newsworthy / Employee Events Notification Time Limit Security related events requiring one hour reporting to the One hour NRCOC are contained in SDP-IOO, Safeguards Event Reporting. Any event or situation related to the health and safety of the Four hours public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made (excludes contaminated groundwater incidents as described in ). Fitness For Duty Event 24 hours W2002/AWT/cls/cls/cls Notes The Security Manager or designee will inform the Shift Manager of notifications made and actions taken. The Shift Manager will notifY the NRCOC of security related events requiring one hour notifications. 10CFR 73.7IJa & bl Examples of newsworthy events are: Inadvertent release of radioactively contaminated materials. Any notification to a government agency. On-site fatality, or injury to three or more individuals all requiring in-patient hospitalization. OSHA regulations (29 CFR 1904.39) require reporting onsite fatalities, or the death of an employee from a work-related incident, or the in-patient hospitalization of 3 or more employees as a result of a work-related incident, within 8 hours. The OSHA phone number is listed in the Emergency Response Directory (Government Organizations Section). Assure the Duty Safety Supervisor is aware of this OSHA notification requirement. Assure the Shift Manager follows up with an NRC notification. 10CFR 50.72(b)(2)(xi) Examples are: Sale, use, or possession of illegal drugs or alcohol within the Protected Area. Any acts by any person licensed under 10CFR Part 55 to operate a power reactor, or by any supervisory person assigned to perform duties within the scope of this part (1 OCFR Part 26), such as: o Sale, use, or possession of a controlled substance o Positive tests on such persons o Use of alcohol within the Protected Area o Unfit for duty due to the consumption of alcohol 10CFR26.73,0-ADM-018

Procedure No.: Procedure

Title:

Page: 16 Approval Date: 0-ADM-115 Notification of Plant Events 5/15/08 ENCLOSURE 1 (Page 7 of7) NRC NOTIFICATION TABLE Followup Notification Notification Time Limit In addition to the initial notification, the Shift Manager shall lOne hour make followup notifications for the following conditions: Further degradation in the level of safety of the plant or other worsening plant condition. The results of ensuing evaluations or assessments of plant conditions. The effectiveness ofresponse or protective measures taken. Any information related to plant behavior that is not understood. W2002/AWT/cls/cls/cls Notes The NRC may request an open channel for followup notifications. The time frame for followup reports will be based on NRC recommendations made during the initial report and on the judgment of the Shift Manager as to the seriousness of the event. All followup reports shall be made within 1 hour. 10CFR 50.72(c)(1)(i), 50.72(c)(2)(i), 50.72(c)(2)(ii), 50.72(c)(2)(iii), 50.72(c)(3). Procedure No.: Procedure

Title:

Page: 16 Approval Date: 0-ADM-115 Notification of Plant Events 5/15/08 ENCLOSURE 1 (Page 7 of7) NRC NOTIFICATION TABLE Followup Notification Notification Time Limit In addition to the initial notification, the Shift Manager shall One hour make followup notifications for the following conditions: Further degradation in the level of safety of the plant or other worsening plant condition. The results of ensuing evaluations or assessments of plant conditions. The effectiveness of response or protective measures taken. Any information related to plant behavior that is not understood. W2002/AWTlcls/cls/cls Notes The NRC may request an open channel for followup notifications. The time frame for followup reports will be based on NRC recommendations made during the initial report and on the judgment of the Shift Manager as to the seriousness of the event. All followup reports shall be made within I hour. 10CFR 50.72(c)(1)(i), 50.72(c)(2)(i),

50. 72( c)(2)(ii), 50. 72( c )(2)(iii), 50. 72( c)(3).

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 : Radioactive Gaseous Effluent Monitoring Instrumentation, Operability and Alarmrrrip Setpoints, (continued)

2.

TABLE 3.1-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT Condenser Air Ejector Vent System

a.

Noble Gas Activity Monitor (SPING or PRMS)

b.

Iodine Sampler

c.

Particulate Sampler MINIMUM CHANNELS OPERABLE 1 1 1

d.

Effluent System Flow Rate Measuring Device 1

e.

Sampler Flow Rate Measuring Device 1 3 - 11 APPLICABILITY ACTION 3.1.3 3.1.6 3.1.6 3.1.2 3.1.5 6/4/07 Co TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 : Radioactive Gaseous Effluent Monitoring Instrumentation, Operability and AlarmfTrip Setpoints, {continued)

2.

TABLE 3.1-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT Condenser Air Ejector Vent System

a.

Noble Gas Activity Monitor (SPING or PRMS)

b.

Iodine Sampler

c.

Particulate Sampler MINIMUM CHANNELS OPERABLE 1 1 1

d.

Effluent System Flow Rate Measuring Device 1

e.

Sampler Flow Rate Measuring Device 1 3 - 11 APPLICABILITY ACTION 3.1.3 3.1.6 3.1.6 3.1.2 3.1.5 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 : Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and Alarmrrrip Setpoints, (continued) TABLE 3.1-1 (continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE

3.

Plant Vent System (Include Unit 4's Spent Fuel Pool)

a.

Noble Gas Activity Monitor (SPING or PRMS)

b.

Iodine Sampler

c.

Particulate Sampler

d.

Effluent System Flow Rate Measuring Device 1

e.

Sampler Flow Rate Measuring Device

4.

Unit 3 Spent Fuel Pit Building Vent

a.

Noble Gas Activity Monitor

b.

Iodine Sampler

c.

Particulate Sampler

d.

Sampler Flow Rate Measuring Device 1 1 1 1 1 1 1 1 3 - 12 APPLICABILITY ACTION 3.1.3 3.1.4 3.1.4 3.1.2 3.1.5 3.1.3 3.1.4 3.1.4 3.1.5 6/4/07 TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 : Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and Alarmrrrip Setpoints, (continued) TABLE 3.1-1 (continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE

3.

Plant Vent System (Include Unit 4's Spent Fuel Pool)

a.

Noble Gas Activity Monitor (SPING or PRMS)

b.

Iodine Sampler

c.

Particulate Sampler

d.

Effluent System Flow Rate Measuring Device 1

e.

Sampler Flow Rate Measuring Device

4.

Unit 3 Spent Fuel Pit Building Vent

a.

Noble Gas Activity Monitor

b.

Iodine Sampler

c.

Particulate Sampler

d.

Sampler Flow Rate Measuring Device 1 1 1 1 1 1 1 1 3 - 12 APPLICABILITY ACTION 3.1.3 3.1.4 3.1.4 3.1.2 3.1.5 3.1.3 3.1.4 3.1.4 3.1.5 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 : Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and AlarmlTrip Setpoints, (continued) TABLE 3.1-1 (Continued) TABLE NOTATION At all times. Applies during MODE 1, 2, 3 and 4. Applies during MODE 1, 2, 3 and 4 when primary to secondary leakage is detected. ACTION 3.1.2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION 3.1.3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours. ACTION 3.1.4 SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLE EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours of the start of the SAMPLING EVOLUTION. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided continuous sample collection with auxiliary equipment as required by Table 3.2-1 is installed within 4 hours of the channel being declared INOPERABLE, and analyzed at least weekly. 3 - 13 6/4/07 TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 : Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and AlarmfTrip Setpoints, (continued) TABLE 3.1-1 (Continued) TABLE NOTATION At all times. Applies during MODE 1, 2, 3 and 4. Applies during MODE 1, 2, 3 and 4 when primary to secondary leakage is detected. ACTION 3.1.2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION 3.1.3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours. ACTION 3.1.4 SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLE EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours of the start of the SAMPLING EVOLUTION. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided continuous sample collection with auxiliary equipment as required by Table 3.2-1 is installed within 4 hours of the channel being declared INOPERABLE, and analyzed at least weekly. 3 - 13 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT ACTION 3.1.5 ACTION 3.1.6 SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLING EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours of the start of the SAMPLING EVOLUTION. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided auxiliary equipment is installed, AND the sample flow rate is verified at least once per 4 hours. Continuous collection of iodine and particulate in the Cqndenser Air Ejector is not required. If Primary to Secondary leakage is detected, effluent releases via the affected pathway may continue provided that the iodine and particulate curies released are determined using the methodology of Reference 3. SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLING EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours of the start ofthe SAMPLING EVOLUTION. 3 - 14 6/4/07 TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT ACTION 3.1.5 ACTION 3.1.6 SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLING EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours of the start of the SAMPLING EVOLUTION. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided auxiliary equipment is installed, AND the sample flow rate is verified at least once per 4 hours. Continuous collection of iodine and particulate in the Cqndenser Air Ejector is not required. If Primary to Secondary leakage is detected, effluent releases via the affected pathway may continue provided that the iodine and particulate curies released are determined using the methodology of Reference 3. SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLING EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours of the start of the SAMPLING EVOLUTION. 3 - 14 6/4/07

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 Surveillance 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 Surveillance Requirement specified in Table 4.3-1. TURKEY POINT - UNITS 3 & 4 3/4 3-1 AMENDMENT NOS. 178AND 172

TABLE 3.3-1 c

0 A

m REACTOR TRIP SYSTEM INSTRUMENTATION "1J 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 C/) 2 1 2 3*,4*,5* 9 Vl 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 Vl

a.

Startup 2 1 2 2# 4 ~

b.

Shutdown** 2 0 2 3,4,5 5 Vl

c.

Shutdown 2 1 2 3*,4*,5* 9 N

5.

Overtemperature !:J. T 3 2 2 1,2 13

6.

Overpower !:J. 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 CJ f) f) ~ 0

9.

Pressurizer Water Level--High 2 C/) (Above P-7) ~ 0

10. Reactor Coolant Flow--Low z

a.

Single Loop (Above P-B) 3/loop 2/loop 2/loop 6 0 b. Two Loops (Above P-7 3/loop 2/1oop 2/loop 6 Vl and below P-B) 01 ~ c TABLE 3.3-1

u A

m REACTOR TRIP SYSTEM INSTRUMENTATION "0 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 1,2 ~ 2 1 (f) 2 1 2 3*,4*, 5* 9 w 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 2 1##, 2 3

4.

Source Range, Neutron Flux w

a.

Startup 2 1 2 2# 4 ~

b.

Shutdown** 2 0 2 3,4,5 5 w

c.

Shutdown 2 1 2 3*,4*, 5* 9 I N

5.

Overtemperature /:I. T 3 2 2 1,2 13

6.

Overpower /:I. 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 () (') 9 f:l 0

9.

Pressurizer Water Level--High 2 t 1 (f) (Above P-7) ,--/ 0

10. Reactor Coolant Flow--Low z

a.

Single Loop (Above P-B) 3/100p 2/100p 2/100p 6 0

b.

Two Loops (Above P-7 3/1oop 2/100p 2/1oop 6 w and below P-B) (Jl

-l TABLE 3.3-1 (Continued) c

0 A

REACTOR TRIP SYSTEM INSTRUMENTATION m "U MINIMUM 0 TOTAL NO. CHANNELS CHANNELS APPLICABLE z -l 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 =i Level--Low-Low (j) w Qo

12. Steam Generator Water Level--

2 stm. gen. 1 stm. gen. 1 stm. gen. 1,2 6 .po. Low Coincident With Steam! level and level coin-level and Feedwater Flow Mismatch 2 stm.lfeed-cident with 2 stm.lfeed-water flow 1 stm.lfeed-water flow mismatch in water flow mismatch in each stm. gen. mismatch in same stm. gen. w same stm. or 2 stm. gen. 1: gen. level and 1 w stm.Ifeedwater I w flow mismatch in same stm. gen.

13. Undervoltage--4.16 KV Busses 2/bus 1/bus on 2/bus 12 s::

m A and B (Above P-7) both busses z 0 s::

14. Underfrequency-Trip of Reactor 2/bus 1 to trip 2/bus 11 m

z Coolant Pump Breaker(s) Open RCPs*** -l (Above P-7) z 0 (j)

15. Turbine Trip (Above P-7) w

a.

Autostop Oil Pressure 3 2 2 12 ""-l

b.

Turbine Stop Valve Closure 2 2 2 12 z 0 W N -l TABLE 3.3-1 (Continued) c

0 A

REACTOR TRIP SYSTEM INSTRUMENTATION m lJ MINIMUM 0 TOTAL NO. CHANNELS CHANNELS APPLICABLE z -l 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 =i Level--Low-Low (J) w R<>

12. Steam Generator Water Level--

2 stm. gen. 1 stm. gen. 1 stm. gen. 1,2 6 ./>0. Low Coincident With Steam! level and level coin-level and Feedwater Flow Mismatch 2 stm.lfeed-cident with 2 stm.Ifeed-water flow 1 stm.Ifeed-water flow mismatch in water flow mismatch in each stm. gen. mismatch in same stm. gen. w same stm. or 2 stm. gen.

J;;:

gen. level and 1 w stm.Ifeedwater I w flow mismatch in same stm. gen.

13. Undervoltage--4.16 KV Busses 2!bus 1!bus on 2!bus 12 m

A and B (Above P-7) both busses z 0

14. Underfrequency-Trip of Reactor 2!bus 1 to trip 2!bus 11 m

z Coolant Pump Breaker(s) Open RCPs*** -l (Above P-7) z 0 !'fJ

15. Turbine Trip (Above P-7) w

a.

Autostop Oil Pressure 3 2 2 1 12 -...J

b.

Turbine Stop Valve Closure 2 2 2 1 12 z 0 W N

TABLE 3.3-1 (Continued) --l c REACTOR TRIP SYSTEM INSTRUMENTATION

0 m

MINIMUM "U TOTAL NO. CHANNELS CHANNELS APPLICABLE 0 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Z --l I

16. Safety Injection Input c

from ESF 2 2 1,2 8 z ~ en

17. Reactor Trip System Interlocks w

!(O

a.

Intermediate Range .j:>. Neutron Flux, P-6 2 2 2# 7

b.

Low Power Reactor Trips Block, P-7 P-10 Input 4 2 3 1 7 or Turbine First 2 2 7 w Stage Pressure ~ w Power Range Neutron c. .j:>. 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

5:

m Position Trip z Above P-8 1/breaker 1 1/breaker 1 11 0

a.

s::

b.

m Above P-7 and below P-8 1/breaker 2 1/breaker 1 11 z --l

19. Reactor Trip Breakers 2

1 2 1,2 8,10 z 2 1 2 3*,4*,5* 9 0 en

20. Automatic Trip and Interlock 2

2 1,2 8 co logic 2 2 3*,4*,5* 9 z 0 N TABLE 3.3-1 (Continued) -i c REACTOR TRIP SYSTEM INSTRUMENTATION

u A m MINIMUM

-0 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 (f)

17. Reactor Trip System Interlocks w

Qo

a.

Intermediate Range .j:>. 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 2 7 w Stage Pressure

i>:

w Power Range Neutron

c.

.j:>. Flux, P-8 4 2 3 7

d.

Power Range Neutron Flux, P-10 4 2 3 1,2 7

18. Reactor Coolant Pump Breaker m

Position Trip z Above P-8 1/breaker 1 1/breaker 11 0

a.

b.

Above P-7 and below P-8 1/breaker 2 1/breaker 11 m z -i

19. Reactor Trip Breakers 2

2 1,2 8, 10 z 2 2 3*,4*, 5* 9 0 (f) -...,J

20. Automatic Trip and Interlock 2

2 1,2 8 (Xl logic 2 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 hours or be in HOT STANDBY within the next 6 hours. 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 hours,

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours 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 hours; or, the QUADRANT POWER TILT RATIO is monitored per Specification 4.2.4.2. TURKEY POINT - UNITS 3 & 4 3/4 3-5 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 hours or be in HOT STANDBY within the next 6 hours. 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 hours,

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours 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 hours; or, the QUADRANT POWER TILT RATIO is monitored per Specification 4.2.4.2. TURKEY POINT - UNITS 3 & 4 3/4 3-5 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 hour and at least once per 12 hours 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 hours. ACTION 7 - With less than the Minimum Number of Channels OPERABLE, within 1 hour 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 hours; however, one channel may be bypassed for up to 2 hours 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 hours 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 hours 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 (I ntermediate 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 hour and at least once per 12 hours 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 hours. ACTION 7 - With less than the Minimum Number of Channels OPERABLE, within 1 hour 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 hours; however, one channel may be bypassed for up to 2 hours 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 hours 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 hours 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 hours. 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 hours. 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 hours. For subsequent required DIGITAL CHANNEL OPERATIONAL TESTS the inoperable channel may be placed in bypass status for up to 4 hours. TURKEY POINT - UNITS 3 & 4 3/43-7 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 hours. 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 hours. 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 hours. For subsequent required DIGITAL CHANNEL OPERATIONAL TESTS the inoperable channel may be placed in bypass status for up to 4 hours. TURKEY POINT - UNITS 3 & 4 3/4 3-7 AMENDMENT NOS. 179 AND 173}}

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