ML100670324
| ML100670324 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/11/2009 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| 50-250/09-302, 50-251/09-302 50-250/09-302, 50-251/09-302 | |
| Download: ML100670324 (79) | |
Text
FACILITY NAME: Turkey Point Section 8 REPORT NUMBER: 2009-302 FINAL RO WRITTEN EXAM CONTENTS:
./
GJ/ Final RO Written Exam (75 'as given' questions with changes made during administration annotated)
Q Reference Handouts Provided To Applicants u;y' Answer Key Location of Electronic Files:
SubrnittedBy:,d,~.b ~#
VerifiedBy1JZJl U~
FACILITY NAME: Turkey Point Section 8 REPORT NUMBER: 2009-302 FINAL RO WRITTEN EXAM CONTENTS:
./
GJ/ Final RO Written Exam (75 'as given' questions with changes made during administration annotated)
Q Reference Handouts Provided To Applicants u;y' Answer Key Location of Electronic Files:
Submitted By: ~ih ~;# verifiedBy1r!Jj-ti~
ES-401 Name:
Date:
Site-Specific RO Written Examination Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination A~licant Information Form ES-401-7 Facility/Unit: TurkeJl 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 no KEY 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 0
74 D
19 A
75 B
20 B
6 21 A
22 B
23 B
7 24 B
8 25 D
81 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
l 40 D
96 41 C
97 42 B
9 43 A
9 44 C
1 0 45 C
46 C
47 C
48 C
49 D
50 C
51 C
52 0
53 A
54 D
55 C
56 B
Turkey Point ILC 25 no KEY 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 0
74 D
19 A
75 B
20 B
6 21 A
22 B
23 B
7 24 B
8 25 D
81 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
l 40 D
96 41 C
97 42 B
9 43 A
9 44 C
1 0 45 C
46 C
47 C
48 C
49 D
50 C
51 C
52 0
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 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 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-I, 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 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-I, 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-I, 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 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-I, 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.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 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'-0'-) __ 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-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 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:
y RCS pressure is 350 psig y RCS temperature is 115°F y Time since shutdown - 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> Subsequently, RHR has been lost.
In accordance with 0-ADM-051, Figure 1, Outage Risk Assessment and Control, Typical heat Up Rates wNessel 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:
y RCS pressure is 350 psig y RCS temperature is 115°F y Time since shutdown - 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> Subsequently, RHR has been lost.
In accordance with 0-ADM-051, Figure 1, Outage Risk Assessment and Control, Typical heat Up Rates wNessel 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 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 _--:C--=l..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 _---'(>...::1..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 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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) stearn introduction into the CCW System B
(1) stearn introduction into the RCP Seal Return (2) stearn introduction into the CCW System C
(1) stearn 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) stearn introduction into the CCW System B
(1) stearn introduction into the RCP Seal Return (2) stearn introduction into the CCW System C
(1) stearn 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 invol ve 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 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 invol ve 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 Panel 3P07.
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 R WST.
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 Panel 3P07.
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 R WST.
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 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-l.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-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
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.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
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.
R WST 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.
R WST 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 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 _---'Cl..-"I'-'-) __ 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 increase C
hot leg cooldown D
hot leg pressure increase
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 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 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 Ll.H 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 Ll.H 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, 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 LT-4-459 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 LT-4-459 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 (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 23 The A Monitor Tank (MT) is being released when the following occurred:
- Annunciator H 114 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-OI8 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 23 The A Monitor Tank (MT) is being released when the following occurred:
- Annunciator H 114 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-OI8 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 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 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.
R WST 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-&/t/IIi>T-I/-r~
.2L~ Ito-f J. R79 f?-.~:>#";.;!
- ~/1$h7///.J?-S A
QSPDS Train B is indicating properly.
Complete 4-EOP-FR-C.2 then return to procedure and step in effect.
B QSPDS Train B is indicating properly.
Stop performance of 4-EOP-FR-C.2 and return to procedure and step in effect.
C QSPDS Train B is NOT indicating properly. Thots are affected by the Safety Injection flow.
Manually calculate subcooling.
D QSPDS Train B is NOT indicating properly. PT-4-406 has failed to approximately 2210 psig.
Manually calculate subcooling.
Turkey Point ILC 25 Question 25 Initial Conditions:
Unit 4 was at 100% power.
4A QSPDS has been declared inoperable because of a PT-4-404 failure.
Subsequently:
Unit 4 experienced a LOCA with Safety Injection.
50 gpm is indicated on FI-4-943, Safety Injection Flow.
R WST level is also decreasing at 50 gpm.
The crew entered 4-EOP-FR-C.2, Degraded Core Cooling.
QSPDS Train B now indicates the following:
Thots are all approximately 525°F.
RCS subcooling is 126°F.
Which of the following correctly describes QSPDS Train B indication and required action(s)?
.PT-'i-&/t/IIi>T-I/-r~
.2L~ Ito-f J. R79 f?-.~:>#";.;!
- ~/1$h7///.J?-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 running. 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 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 running. 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 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 V CT 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 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 V CT 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 seal leakoff flow 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 seal leakoff flow 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
Turkey Point ILC 25 Question 31 Unit 3 is in Mode 6.
The crew is preparing to drain the refueling cavity to the R WST.
One RHR Pump is running.
What effect will fully opening 3-887, RHR to RWST Hdr Isol Valve, have on the RHR System?
Flow indicated on FI-3-605, RHR Hx Outlet Flow Indicator, will (1)
. Flow to the core will (2)
(1)
(2)
A decrease remain the same B
decrease decrease C
mcrease 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 R WST.
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-->..;(lo..,L) __ ' Flow to the core will (2)
(1)
(2)
A decrease remain the same B
decrease decrease C
mcrease remain the same D
increase 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 foIl owing 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 foIl owing identifies the operability of the 3A SI Accumulator and why?
The 3A SI accumulator is...
A OPERABLE. AIl 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 foIl owing 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 foIl owing identifies the operability of the 3A SI Accumulator and why?
The 3A SI accumulator is...
A OPERABLE. AIl 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.
PRT 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.
PRT 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 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 3AB19 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: 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 3AB19 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)?
(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.
Train 4B RPS testing is in progress. h-i5.; trSf biP'-19 n The 4B Reactor Trip Bypass Breaker)8Jacked 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. h-i5.; trSf biP'-19 n The 4B Reactor Trip Bypass Breaker)8Jacked 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 Panel3P06 B
3-0NOP-003.7, Loss of 120V Vital Instrument Panel 3P07 C
3-0NOP-003.8, Loss of 120V Vital Instrument Panel 3P08 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 Panel3P06 B
3-0NOP-003.7, Loss of 120V Vital Instrument Panel 3P07 C
3-0NOP-003.8, Loss of 120V Vital Instrument Panel 3P08 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 (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 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 I~ection, 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 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 I~ection, 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 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 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 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-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.
o The CSPs will NOT start.
MOV-4-880 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-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.
o The CSPs will NOT start.
MOV-4-880 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:
y Annunciator C 2/1, SG A NARROW RANGE HI LEVEL y Annunciator C 5/1, SG A STEAM> FEED y 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 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 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:
y Annunciator C 2/1, SG A NARROW RANGE HI LEVEL y Annunciator C 5/1, SG A STEAM> FEED y 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 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/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.
S ubsequentl y:
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 3 A and 3 B EDGs start.
What is the status of the Unit 3 4kV Buses?
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.
S ubsequentl y:
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 3 A and 3 B EDGs start.
What is the status of the Unit 3 4kV Buses?
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 DCS?
4D01 4D23 A
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hours B
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C
greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2 hours D
greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 DCS?
4D01 4D23 A
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hours B
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C
greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2 hours D
greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
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 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 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 100/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
mRlhr Crud D
mRlhr Fission products Turkey Point ILC 25 Question 52 Chemistry reports an increase in gross equivalent iodine and 100/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
mRlhr Crud D
mRlhr 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°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-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-I00, 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-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-I00, Fast Load Reduction.
Turkey Point ILC 25 Question 54
, (j PIN has experienced a dual-unit loss of off-site power. - ~
("'~-v) /.:,f fev c::/ I" The 3B EDG did not start.
~/<J{J- ~n&"l;'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
, (j PIN has experienced a dual-unit loss of off-site power. - ~
("'~-v) /.:,f fev c::/ I" The 3B EDG did not start.
~/<J{J- ~n&"l;'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 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 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 56 HCV 121, Charging Flow to Regen Heat Exchanger Control Valve, is full open.
How is the controller for H CV 121 adjusted to decrease charging line flow under nonnal conditions and how does HCV 121 fail on loss of Instrument Air?
The demand on the controller for H CV 121 is (1) to decrease charging line flow. HCV 121 fails (2) on loss of Instrument Air.
(1)
(2)
A decreased from 1 00%
Open B
increased from 0%
Open C
decreased from 1 00%
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 H CV 121 adjusted to decrease charging line flow under nonnal conditions and how does HCV 121 fail on loss of Instrument Air?
The demand on the controller for H CV 121 is (1) to decrease charging line flow. HCV 121 fails (2) on loss of Instrument Air.
(1)
(2)
A decreased from 1 00%
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:
y 4V20, Unit 4 Containment Purge Exhaust Fan y 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:
y 4V20, Unit 4 Containment Purge Exhaust Fan y 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 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-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.
o 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.
o 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-OI8 respond when the RO resets the Hi Alarm on the respective PRMS drawers?
NOTE:RCV-OI4 is Gaseous Release Header Isolation Valve RCV -018 is Liquid Release Header Isolation Valve RCV-014 RCV-OI8 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-OI8 respond when the RO resets the Hi Alarm on the respective PRMS drawers?
NOTE:RCV-OI4 is Gaseous Release Header Isolation Valve RCV -018 is Liquid Release Header Isolation Valve RCV-014 RCV-OI8 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 HV AC 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 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 HV AC 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 eTO) 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 O-ADM-IOO, 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 eTO) 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 O-ADM-IOO, 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.
BYes; 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.
BYes; 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 C{!'r Lt)r7?~'f,v~" n/j tin/! ~ vP/U////~
Installing temporaryr\\'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 Dnit 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 C{!'r Lt)r7?~'f,v~" n/j tin/! ~ vP/U////~
Installing temporaryr\\'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 Dnit 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 69 Units 3 and 4 have both simultaneously lost 120V Panel POS.
How will the Feed Regulating Valves (FRVs) respond on each unit?
Unit 3 Unit 4 A
A S/O Lock up Auto B S/O Auto Auto C S/O Manual Manual B
A S/O Auto Lock up B S/O Auto Auto C S/O Manual Manual C
A S/O Auto Lock up B S/O Lock up Lock up C S/O Auto Lock up o
A S/O Lock up Auto B S/O Lock up Lock up C S/O Lock up Auto Turkey Point ILC 25 Question 69 Units 3 and 4 have both simultaneously lost 120V Panel POS.
How will the Feed Regulating Valves (FRVs) respond on each unit?
Unit 3 Unit 4 A
A S/O Lock up Auto B S/O Auto Auto C S/O Manual Manual B
A S/O Auto Lock up B S/O Auto Auto C S/O Manual Manual C
A S/O Auto Lock up B S/O Lock up Lock up C S/O Auto Lock up o
A S/O Lock up Auto B S/O Lock up Lock up C S/O 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:
y 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 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:
y 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 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 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 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 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 OP ~ T actuation D
Loss of 120 VAC Panel3POS 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 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 OP ~ T actuation D
Loss of 120 VAC Panel3POS
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 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 15t 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 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 15t 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.
S I 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 perfonnance 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 perfonnance 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.
S I 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 perfonnance 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 perfonnance of the main body of the procedure.
D In 4-EOP-E-2, Faulted Steam Generator Isolation, when the Fold Out Page is directed.
Procedure No.:
O-ADM-OSI W97:DJTllnlnw/ln Procedure
Title:
c E
LL o
I (J) ill o
ill
+-
CD 0:::
0...
- J
+-ro ill I
4,0 3,5 3,0 2.5 2.0 1.5 1.0 0,5 0,0 Page:
39 Approval Date:
Outage Risk Assessment and Control FIGURE 1 (Page 1 of 1)
TYPICAL HEAT UP RATES WNESSEL FULL
--r -, - - - -,- - - - - T - - - - -,- - - - - - - -,- - - - -,- - - - - T - - - - -,- - - - - i - - - - -,- - - - - i - - - - - i I
I I
I I
f I
I I
I I
I
-+ -Q- __ 0004 _____.. _____ 1 _____.J, _____ '- ____ ~ _____.... _____ 1 _____ "' _____ I- ____ ~ _____ I t
I I
I I
I I
I I
I I
I I
I I
I I
t f
I I
I I
I I
I I
I I
I I
-+ _I ~ _ ~ _____ ~ _____ : _____ ~ _____ ~ ____ ~ _____ ~ _____ : _____ J _____ ~ ____ ~ _____ :
\\ -\\\\
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
.J _____ 1. _____, _____.J. _____ L ____.J _____ L _____, _____ J. _____ L ____.J _____ I I
I I
I I
I I
I I
I I
I f
I
-- -\\~\\ -- -~---- -:- ---- ~- ----~----~--- -- ~ -- -- -:-- - --~- -- --~- --- ~- ----!
1 I
I I
I I
I I
I I
J I
V I
I I
I I
I I
I I
I I
I I
I I
'\\
: -"\\ ---t -
-'---- ----;- ----., -----t -- -- -: -- -- -+ -----:- ---- - - - - i I
I I
~
I
~_ I
- -=
--- --f- -- _ -+----"'"'::.,_--- ~- ----~~
____ ~ _____ 1 _____ + _____ 1-_ - __... ___ --I I
I I
I 1- -..J...
I r
I '
I I
L
--r- ~
.-: ~
I I
I I
I
_1_
1 I
t
: ----- ~ -----:----- ~ -----~ ---- ~ ----- ~ ---= --::-~ -~ -i-- ---:- -- ::-~ =-----;
I I
I o
5 10 15 20 25 30 35 1
40 45 I
50 55 60 Time Since Shutdown (Oa~s) 150 MWD/MTU B/U -
B/U B/U -
7,1300 MWO/MTU 16,5013 MWD/MTU 8/29/07 Procedure No.:
O-ADM-OSI W97:DJTllnlnw/ln Procedure
Title:
~
c E
LL o
I (J) ill o
ill
+-
CD 0:::
0...
- J
+-ro ill I
4,0 3,5 3,0 2.5 2.0 1.5 1.0 0,5 0,0 Page:
39 Approval Date:
Outage Risk Assessment and Control FIGURE 1 (Page 1 of 1)
TYPICAL HEAT UP RATES WNESSEL FULL
~-----T-----I-----l-----r----l-----T----~-----T-----~----l-----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
I I
I I
I f
I I
I I
I I
_ _ 0004 _____.. ___ __ 1 _____.J, _____ '- ____
~ _____.... ___ __ 1 ____ _ "' ___ __ I- ____ ~ _____ I I
I I
I I
I t
f I
I I
\\
\\
t I
I I
I I
I I
I I
I I
I I
I I
I I
I I
-\\~ -~ -----~ -----:-----~ -----~ ----~ -----~ -----:-----J -----~ ----~ -----:
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
I I
I I
I I
I I
I I
I
.J _____ 1. _____, _____.J. _____ L ____.J _____ L _____, _____ J. _____ L ____.J _____ I I
I I
I I
I I
I I
I I
I 1
I I
I I
I I
f I
I I
I I
I I
I 1
I I
I I
I I
I f
I I
I I
I I
I
- -\\ -1
~ -
~ -
- ~ -
- ~ -
_ - __ ~ ___ __ : _____ ~ _____ ~ ____ ~ _____ !
1 I
I I
I I
I I
I I
J I
V I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
- \\
I t ' I I
I I
I I
l I
~-~---T-I I
J I
I I
I I
t I
I I
~
~ -
~- -
- -! ----- ~
-..1
'~
1 1
~_:
- -=1
f--- __ + ____
"'"'::.I_---~ _____ ~~
~
I
~
~
- - ~ - - ~
y-~
-=-I-----~-----~----!-----!
I I
I I
I --L I
,--r-~----.-:
I I
I I
t
_1_
1 I
.........-==
: ----- ~ -----:----- ~ -----~ ---- ~ ----- ~ ---= --::-~ -~ -i-- ---:- -- ::-~ =-----;
I I
I I
1 I
I I
I I
I I
I I
I I
I J
J I
I I
1 I
I 1
I I
I I
I I
I I
I I
I I
I 1
I I
I I
I I
o 5
I 10 I
15 20 25 I
30 I
35 I
40 I
45 I
50 I
55 I
60 Time Since Shutdown (Oa~s) 150 MWD/MTU B/U -
B/U B/U -
7,1300 MWO/MTU 16,5013 MWD/MTU 8/29/07